Rev 00, March 29, 2012 Page 1 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

White Paper:

LANL Neutron-to-Photon (NP) Dose Ratio 

Analysis

Rev. 00; March 29, 2012

Prepared by:

Jack Fix
Rev 00, March 29, 2012 Page 2 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Introduction:

This White Paper describes analyses performed to calculate the statistical parameters of 

lognormal distributions of neutron-to-photon (NP) dose ratios using LANL provided recorded 

doses for LANL workers (SRDB reference 27261) during the period of 1944 through November 

2008. This information extends information contained in ORAUT-TKBS-0010-6 (2009), “Los 

Alamos National Laboratory – Occupational External Dose. 

Purpose:

The purpose of this white paper is to document the method of analysis, and to present the 

calculated statistical lognormal distribution parameters [i.e., Geometric Mean (GM), Geometric 

Standard Deviation (GSD) and the 95th Percentile] for each year and selected multi-year 

periods. 

Method:

The analysis of neutron to photon (NP) dose ratios for LANL workers used the LANL recorded 

dose data contained in SRDB 27261. Only annual neutron and photon doses, respectively, that 

equal or exceed 50 mrem were used. The analysis results are presented in SRDB 104692.

Summary:

The calculated NP dose ratio parameters for each year from 1950 through 2008 are presented 

in Table A-1, Attachment A (SRDB 104692). The pattern in the GM and 95th Percentile 

parameters are shown in Figure 1 with inclusion of significant events obtained from the history 

of LANL dosimetry presented in Attachment B. A documented personal communication with a 

LANL external dosimetry site and subject expert, who performed many workplace dose 

measurements and evaluations, was also done (SRDB reference 107058). The statistical 

parameters, presented in Table A-1, are based on 412,000 (1950-2008) measured annual dose

results. Significant events noted in Figure 1 include:

 Implementation of the use of Kodak Nuclear track emulsion type A (NTA) in 1951

(Littlejohn 1960). LANL had earlier used a very similar nuclear track emulsion glass 

plate for routine dosimetry. The use of NTA to measure neutron dose continued until 

1995 when the routine use of track-etch dosimetry (TED) was implemented.

 LANL had available an instrument capability to measure the neutron dose equivalent in 

rem which was used in 1963 (Hankins 1963). This capability provides a means to 

assess the performance of dosimeter measured workplace doses with an accurate 

instrument measurement.

 LANL introduced thermoluminescent dosimetry (TLD) capabilities over a period of many 

years. The earliest noted studies occurred in 1970 (Hankins 1969) whereas regular 

assignment of TLDs to all workers was occurring in 1978 (Lawrence 1978).

 LANL participated in performance testing of the standard that eventually was issued as 

ANSI/HPS N13.11 in 1983. This standard formed the basis of the DOE Laboratory 

Accreditation Program (DOELAP) for personnel dosimetry. LANL was DOELAP 

accredited in 1985 for requested DOELAP categories.
Rev 00, March 29, 2012 Page 3 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

 LANL implemented updated TLD capabilities with the Bicron/Harshaw 8823 system in 

1998 which also utilizes TED capabilities for selected workers (Hoffman and Mallett 

1999).

Figure 1. Illustration of LANL worker GM and 95th Percentile NP Dose Ratio for 1950-2008.

The data illustrated in Figure 1 can be summarized over selected time periods based on the 

foregoing dosimetry operational considerations. Several options are shown in Table 1.

Table 1. Statistical parameters for selected periods of LANL recorded doses 

Period Description

Neutron-to-Photon Dose Ratio

GM GSD 95th 

Percentile

1950-2008 All years of NTA, TLD or TED dose data 1.04 3.06 6.43

1979-2004 ORAUT-TKBS-0010-6 (2009) time period 1.55 2.73 8.27

1979-2008 ORAUT-TKBS-0010-6 (2009) plus 2005-2008 1.50 2.68 7.77

1980-2008 Era of dosimeter performance testing 1.53 2.66 7.90

1985-2008 DOELAP accredited dosimetry systems 1.60 2.61 8.15

It is evident that neutron dose reconstruction using a distribution with a GM of 1.6 and a GSD of 

2.7 could reasonably be done. 

ORAUT-TKBS-0010-6, Rev 02 (2009):

0

5

10

15

20

25

30

35

1950 1960 1970 1980 1990 2000 2010

Neutron to Photon Dose Ratio

Year

LANL Annual Dose Neutron to Photon Dose Ratio 

N:P Ratio GM

N:P Ratio 95th Percentile

NTA TED

rem-meter

TLD
Rev 00, March 29, 2012 Page 4 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

ORAUT-TKBS-0010-6 (2009), “Los Alamos National Laboratory – Occupational External Dose,”

Table 6-22, contains a summary of recommended NP dose ratios for identified sources of 

neutron radiation. The analyses in this White Paper primarily pertain to Neutron Source Types A 

and D in Table 6-22. Table 6-22 does not present the GSD values which are used as input 

IREP. It is evident from the GM and 95th Percentile values that the results of the current 

analysis and those used in the development of ORAUT-TKBS-0010-6 (2009) recommendations 

are equivalent.

 ORAUT-TKBS-0010-6 Table 6-22. Recommended distributions for neutron-to-gamma ratio.

Neutron source type

Neutron-to-photon dose ratio

Median 95th percentile

A. Plutonium facilities (predominantly Pu-239) 0.7 2.8

B. Plutonium facilities (documented involvement with Pu-238

operations; applies only to 1969 or later; most likely at TA-21, 

TA-3-29 [CMR Building], or TA-55)

3.9 5.5

C. Criticality experiments (>50 m distant) 2.3 2.5

D. Other operations (1979 to 2004) 1.6 6.4

References:

Hankins, D. E., 1963, Monitoring Intermediate Energy Neutrons, Health Phys., Vol. 9, pp. 31-39.

Hankins, D. E., 1969, “Los Alamos Scientific Laboratory Neutron Dosimetry,” Presented at AEC 

Workshop on Personnel Neutron Dosimetry, September 23-24, 1969, BNWL-1340, 

Pacific Northwest Laboratory, Richland, WA [SRDB Ref ID: 11096]

Hoffman, J. M., and M.W. Mallett, 1999, The LANL Model 8823 Whole-Body TLD and 

Associated Dose Algorithm, Health Physics, Vol. 77, No. 5, Supplement, pp. S96-S103. 

Lawrence, J. N. P., Letter to Photodosimetry Evaluation Book, dated September 28, 1978, 

entitled “Reportable TLD Exposures,” Los Alamos National Laboratory, Los Alamos, NM 

[SRDB Ref ID: 8206]

Littlejohn, 1960, Photodosimetry Procedures at Los Alamos, LA-2494, Los Alamos National 

Laboratory, Los Alamos, NM, August, [SRDB Ref ID: 951] 
Rev 00, March 29, 2012 Page 5 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

ATTACHMENT A

Calculated NP Dose Ratio Statistical Parameters, 1944-2008

Table A-1. Summary of statistical analysis of LANL recorded doses (SRDB 104692)

Year

Number of Workers Neutron-to-Photon Dose Ratio

Total 

Monitored

Positive 

Recorded 

Dose

Photon, 

Neutron 

Dose ≥50(a)

Mean Max. GM GSD 95th 

Percentile

1944 9 7 0

1945(b) 812 413 2 139.32 275.00 31.62 1.47 261.43

1946(b) 508 391 7 14.02 16.94 13.93 1.12 16.53

1947 1,237 1004 0

1948 2,080 1383 0

1949 3,177 1817 21 3.32 10.88 2.25 2.32 10.63

1950 3,895 1981 75 4.86 24.00 2.12 2.64 14.78

1951 4,257 2538 142 3.01 25.75 1.32 3.37 11.52

1952 2,366 1262 97 3.81 39.94 2.31 2.08 9.40

1953 1,878 1151 131 1.53 9.18 0.80 3.04 5.45

1954 2,068 1166 99 0.85 5.14 0.48 2.77 2.92

1955 1,984 956 100 0.63 4.80 0.39 2.11 1.62

1956 2,287 1189 112 0.84 8.75 0.49 2.60 2.28

1957 2,539 1054 78 2.66 31.17 0.77 4.87 10.53

1958 3,032 1378 133 1.01 8.27 0.36 4.43 4.29

1959 2,930 1552 186 0.75 11.57 0.37 3.16 2.30

1960 3,622 1718 179 1.04 6.80 0.58 2.44 2.88

1961 3,973 1395 24 0.24 0.83 0.16 2.10 0.63

1962 4,119 2101 45 1.02 4.42 0.49 3.63 3.93

1963 4,176 1702 71 1.01 8.40 0.40 5.36 5.46

1964 4,103 1580 89 0.60 3.38 0.35 2.90 2.02

1965 4,222 1352 101 0.75 10.00 0.40 2.71 2.14

1966 4,446 1514 98 0.53 4.14 0.29 3.41 1.89

1967 4,072 1493 84 0.95 9.60 0.44 3.22 3.42

1968 3,861 2044 114 1.26 9.00 0.62 3.59 4.79

1969 3,980 2679 159 1.18 9.29 0.59 3.17 3.87

1970 4,031 1018 150 0.49 6.80 0.28 2.59 1.48

1971 3,775 806 85 0.48 2.45 0.25 3.24 1.69

1972 3,877 938 127 0.78 5.40 0.39 3.48 2.86

1973 3,866 924 202 0.91 10.20 0.48 2.71 2.67

1974 4,337 1392 250 0.92 18.07 0.42 3.46 3.17

1975 4,716 1874 229 0.67 10.20 0.38 2.91 2.23

1976 5,254 2165 136 0.37 2.80 0.20 3.39 1.42

1977 5,624 1851 130 0.47 8.67 0.22 3.47 1.69
Rev 00, March 29, 2012 Page 6 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Year

Number of Workers Neutron-to-Photon Dose Ratio

Total 

Monitored

Positive 

Recorded 

Dose

Photon, 

Neutron 

Dose ≥50(a)

Mean Max. GM GSD 95th 

Percentile

1978 7,045 2070 135 0.64 6.50 0.29 3.92 2.44

1979 7,549 2511 288 1.14 11.33 0.59 3.33 4.15

1980 7,638 3443 340 1.63 12.80 1.00 2.82 5.51

1981 7,966 5034 463 1.96 14.50 1.30 2.14 5.35

1982 7,997 4297 456 1.89 15.30 1.21 2.19 5.07

1983 8,144 4419 445 1.85 11.57 1.13 2.08 5.00

1984 8,622 6069 535 1.94 11.57 1.26 2.05 5.29

1985 9,487 4921 434 2.63 21.40 1.76 1.94 6.36

1986 9,612 2262 324 3.72 21.40 2.27 2.24 11.59

1987 9,202 1621 253 3.54 17.71 1.99 2.27 10.75

1988 9,469 1548 271 3.68 25.80 1.85 2.58 12.59

1989 10,605 1616 244 3.24 14.33 1.93 2.43 9.58

1990 10,796 1538 207 2.69 14.71 1.64 2.40 8.80

1991 11,284 2356 156 3.05 19.90 1.85 2.28 8.73

1992 11,560 1687 131 2.85 17.24 2.00 2.11 7.29

1993 11,772 1948 132 3.23 15.03 2.34 2.29 9.18

1994 11,783 3145 170 3.38 15.88 2.41 2.19 9.37

1995 12,448 3219 188 3.21 20.92 2.27 2.18 8.21

1996 10,959 2358 197 2.14 11.69 1.57 1.91 5.09

1997 10,860 2992 215 1.86 10.78 1.31 2.50 5.61

1998 11,168 2201 171 1.78 9.16 1.40 2.21 4.50

1999 11,212 1720 158 1.85 8.34 1.40 2.25 4.94

2000 10,456 1485 122 2.10 7.03 1.52 2.07 5.22

2001 10,443 1435 156 1.74 6.91 1.22 2.61 5.39

2002 10,931 1760 199 1.55 6.91 1.07 2.39 4.22

2003 10,752 2101 239 1.57 7.91 1.25 2.66 4.77

2004 10,192 1731 156 1.64 9.86 1.13 2.52 4.79

2005 10,826 2176 193 1.71 7.47 1.29 2.24 4.42

2006 10,104 2021 215 1.93 9.24 1.51 2.21 4.70

2007 9,745 1525 203 1.79 8.01 1.34 2.36 4.73

2008(c) 8,148 941 106 1.48 5.91 1.05 2.52 4.42

a. Number of workers with recorded neutron and deep photon doses, respectively, ≥ 50 mrem.

b. Doses anticipated to have been estimated following accidents and not routinely measured.

c. Anticipated to represent <1 year of dose data (i.e., November 2008 last noted dose entry).
Rev 00, March 29, 2012 Page 7 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

ATTACHMENT B

History of LANL Radiation Associated Events

1944

U.S. Department of Energy, 1997, Linking Legacies, Office of Environmental Management, US 

Department of Energy, Washington, D.C., [SRDB Ref ID: 11930]

Construction of Los Alamos as a centralized laboratory for atomic bomb research and 

production began in November 1942. In March 1943, technicians and scientist began arriving at 

the Laboratory. The laboratory’s mission was the design and manufacture of the first nuclear 

weapons. DP-Site (also known as TA-21), and its successor, TA-55, was built in 1945 as a 

production plant for plutonium bomb cores and polonium-beryllium initiators. DP-Site also 

handled tritium. The DP-Site housed a variety of plutonium research, design, and fabrication 

activities for more than 30 yr until operation of TA-55. TA-55 began operations in 1978. TA-55 

can perform a wide variety of small-scale component fabrication operations, including all of the 

operations that were conducted at Rocky Flats on a large scale. 

Maraman, W. J., W. D. McNeese and R. G. Stafford, 1975, “Confinement Facilities for Handling 

Plutonium,” Health Physics, Vol. 29, pp 469-480.

This paper includes an historical overview of plutonium handling practices at LANL. The earliest 

work with plutonium began in D Building in the old Main Technical Area in the mid-1943 on a 

microgram scale. Multi-gram quantities became available in early 1944. In 1944 and 1945 a 

facility was built at DP Site specifically for chemical and metallurgical work on kilogram 

quantities of plutonium. This facility has been in continuous operation since 1945 until the date 

of this paper in 1975. The program at DP Site in 1975 included metallurgical and chemical 

research and development with 239Pu for the weapons program and the advanced fuels (e.g., 

mixed uranium-plutonium carbides and nitrides) for the Liquid Metal Fast Breeder Reactor 

Program; and recovery of 239Pu from all scrap generated at the LANL; the preparation and 

characterization of 238Pu fuels for the Artificial Heart Program and advanced fuels for Space 

Nuclear Systems; for the recovery of certain reactor-grad plutonium in scrap; and for certain 

studies on the characterization of transuranium waste.

LANL Medical Group, Health Report, August 9, 1943, Manhattan Engineer District, Los Alamos, 

NM [SRDB Ref ID: 29302)

The program of the Medical Group is concerned not only with the specific health problems, i.e., 

the toxic effects of radiation and uranium, but also with the elimination of industrial hazards and 

with the administration of first aid in the technical areas. With regard to the specific health 

problems, the most important deals with the protection of personnel from exposure to 

dangerous amounts of radiation. Our plan is to follow the suggestions of the Chicago Health 

Group, namely, frequent surveys of laboratories to determine radiation intensities, daily record 
Rev 00, March 29, 2012 Page 8 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

of exposure to each person, monthly blood counts (oftener when safe daily dose is exceeded) , 

and semi-annual physical examinations. The problem of preventing poisoning by uranium has 

not been as urgent as above, but routine urinalysis on all persons who will work with this metal 

or radiation will be instituted within the next week.

1944

Los Alamos Dosimetry, “Photodosimetry Evaluation Book "Bible" Volume 1a Procedures 1944-

1959,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8181]

This document provides a tabulation of letters, memorandum, studies, etc., for the LANL 

dosimetry program during the period of 1944 through 1959. The earliest memorandum is dated 

January 19, 1944 from L. H. Hemplemann to S. L. Warren regarding use of film to check 

radiation exposure. 

Hemplemann, L. H., Letter dated May 18, 1944 to S. L. Warren concerning film badge 

dosimeter distribution, “Photodosimetry Evaluation Book "Bible" Volume IA Procedures 

1944-1959,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8181]

This letter states that film monitors have begun to be distributed among the various personnel 

however this has been limited by the fact that only one set of standard exposures arrived in the 

initial shipment. A request is made for more sets of the standard exposures so the film monitors 

could be used regularly.

Los Alamos Dosimetry, “Photodosimetry Evaluation Book "Bible" Volume 1a Procedures 1944-

1959,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8181]

There are several reports describing various aspects of Los Alamos film dosimetry methods. It 

appears from this documentation that capabilities of dosimeters are selected depending upon 

the workplace as follows: 1) a selection of filters (i.e., brass, cadmium, lead, etc., 2) an open 

window for beta radiation (also finger rings and film placed inside gloves), 3) film is processed at 

the University of Rochester, 4) film is exchanged weekly, and 5) recognition of the importance of 

calibrated film and control dosimeters from the same film batch.

Farwall, G., Memorandum entitled “Neutron Yields of Initiator Assemblies Fired to 7/4/1944,” 

Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref ID: 69427]

Eleven active gun assemblies designed by Ayers have been fired by the E-4 20 mm testing 

crew. The neutron emission of each assembly has been measured, after hand assembly where 

possible and after gun assembly in every case. Determination of absolute neutron yields is 

based upon comparison of the active assemblies with a calibrated Po-Be standard. Results are 
Rev 00, March 29, 2012 Page 9 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

estimated to be accurate within ±5%. Comparisons are made with a BF3 detector. An 8% 

correction is made for absorption by the walls of the target assemblies. This correction has 

been determined by comparing the count of the Po-Be standard in the standard paraffin 

geometry to the count of the Po-Be standard placed in a steel target dummy in the position 

occupied by the polonium and beryllium in an active assembly. Differences in target design 

have no measurable effect on the magnitude of the correction.

Breslow, B. A., Memorandum to Distribution, dated June 28, 1944 entitled “Safe Operation of 

the 20 MM Gun Progress Report,” Los Alamos National Laboratory, Los Alamos, NM 

[SRDB Ref ID: 69427]

All workers working with dirty material will wear coveralls, respirator, skull caps and rubber 

gloves. The maintenance of clean clothes and servicing the dirty has been assured.

Los Alamos Dosimetry, “Photodosimetry Evaluation Book "Bible" Volume IB Procedures 1944-

1959,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8266]

This document provides a tabulation of dose algorithms used with LANL dosimeters and 

operating facilities during the period of 1951 through 1959 to evaluate beta and gamma doses. 

The earliest algorithm appears to be Method 1 with starting dates during the period of 

December 24-27, 1944 depending on the facility. The algorithm and processing instruction 

allows a determination of the dosimeter design. Multi-element film dosimeters appear to have 

been used for all facilities.

Lawrence, J. N. P., Letter to File, dated October 6, 1978, entitled “Los Alamos Criticality 

Accidents 1945-19461 Personnel Exposures,” Los Alamos National Laboratory, Los 

Alamos, NM, [SRDB Ref ID: 8206]

The purpose of this memo is to document the exposures to be entered in the H-l Dosimetry

Computer Record for persons involved in the three criticality accidents occurring at Los Alamos 

in 1945-1946. None of the personnel involved wore film badges or other personnel dosimetry 

detectors. Calculations of the personnel exposures exist in several source documents (referred 

to herein), but a simple reference to this material is inadequate because of differences in the 

calculated results. This memo will designate the exposures to be entered in the computer 

record, identify the source documents, point out the differences in the exposure estimates, and 

provide an explanation of why the particular exposure estimates were chosen.

1945

Anonymous, 1956, Film Badge Techniques Prior to 1/1/1952,” Los Alamos National Laboratory, 

Los Alamos, NM, February 16, [SRDB Ref ID: 882]

The information in this reference is dated February 16, 1956, and apparently extracted from 

document that describes the history of LANL dosimetry methods. This reference is specifically 
Rev 00, March 29, 2012 Page 10 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

for the time period prior to 1/1/1952 stating that the various film badge techniques and special 

evaluation methods are provided. Only a few methods were used prior to 1/1/1952. This 

judgment was apparently based on examination of the Accession Books used for film records 

from ?/17/1945 to 2/17/1951 and also by contacting persons who worked at LASL beginning in 

1945. According to summary data, film badges were started at LANL as early as 1943 using 

Eastman Kodak film and a badge with a lead filter. In 1944, a brass filter was being used. 

During the period of 9/10/1948 through 3/11/1949, a new type of film badge was introduced with 

a brass filter and also an unfiltered (open window) region that was regularly used until 

4/20/1950. Calibrations were made using radium and uranium for gamma and beta radiation, 

respectively. Around 8/29/1949, the first nuclear track plates (NTP) were issued for the 

monitoring of fast neutron exposures. The first written reports on fast neutron exposures 

occurred during May 1950. In April 1951, the brass and cadmium filter type of dosimeter holder 

was implemented. 

Dunlap, R. H., Memorandum to Dr. Hemplemann, dated January 1, 1945, entitled “Report on 

room surveys,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref ID: 

40103]

As stated in this reference, “Attached hereto are 66 sheets, consecutively numbered, 

representing the statements of group leaders or room occupants as to the nature of their work 

and toxic materials used. I have prepared a room-by-room index which in all instances refers to 

the proper sheet number. The monitoring procedure, in accordance with the terms in your letter 

dated October 10, 1945, are designated as follows: 

Color Material Monitoring Procedure

Red - 49, Po, or 25 Pluto and swipes daily

Blue - Tuballoy Pluto and swipes daily

White - offices and labs in which 

contamination is possible but not 

probable

swipe monthly

Materials other than Alpha type are so indicated. Inasmuch as many of the rooms indicated by 

red, handle only minute quantities, and these infrequently, or in some instances merely receive 

the material in double bottles, it seems wise that yon and I re-discuss the monitoring procedures 

as it is a rather severe strain to have to monitor these substantially clean rooms by our most 

thorough and time consuming procedure.”

1946

Aebersold, P. C., W. H. Hinch, J. C. Hoffman, and F. W. Molley, 1946, “Radiation Health 

Monitoring,” Los Alamos Technical Series, Los Alamos National Laboratory, Los 

Alamos, NM, January 24, [SRDB Ref ID: 69522]
Rev 00, March 29, 2012 Page 11 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

This is a radiation protection styled document with discussion of radiation, radiation types, 

tolerances, etc. Much of the document provides information and operating instructions for 

several types of portable radiation instruments. Electrical schematics are included for several 

instruments.

1947

Evans, C.E., Letter dated August 4, 1947, to J. W. Newland, University of Rochester, 

concerning description and use of film dosimeters to monitor exposure to workers, Los 

Alamos National Laboratory, Los Alamos, NM [SRDB Ref Id: 8181]

This letter describes the use of LANL constructed brass film holders with varying thickness 

between 4 and 8 (difficult to read) mm with no window or any other metal into which film is 

placed to measure gamma exposure to workers. The film is apparently exchanged monthly. As 

many as three types of film have been used in each badge. One is the Eastman Industrial Type 

K X-ray Safety Film. The second is the DuPont D-C Special Type X-Ray Film which has 

sensitive and insensitive sides and the third is the Adlux Film made also by DuPont which is 

extremely insensitive. Recently only the Eastman film has been used because of good 

experience with this film however for highly hazardous work all three films are used. Generally, 

the tone of this letter is that the method is comparatively successful and more accurate than 

pocket ionization chambers which apparently are also used. The concern was stated that 

exposure could be missed if the dosimeters were not worn by workers and also that too much 

radiation exposure is calculated for contaminated dosimeters. 

Smith, F. S., 1947, Procedure for Pick Up and Disposition of HCT Trash from Bayo Canyon, 

Los Alamos National Laboratory, Los Alamos, NM August 14, [SRDB Ref Id: 37969]

This reference concerns procedures for providing protection to avoid overexposure to 

beta/gamma radiation to the personnel hauling trash and waste from Bayo Canyon to the 

Contaminated Dump. Personnel are to be prepared by the supervisor or Health Instrument 

Escort as follows:

a) Each man will be provided with a film badge containing at least two packets of film of 

different sensitivity.

b) Each man will be provided with two (2) gamma-ray dosimeters.

c) A film badge will be planted in the cab of the contaminated truck.

d) A film badge will be planted in the sedan that makes the trip to the Site.

e) Two red flags are to be mounted on the front of the contaminated truck, two on the rear of 

the contaminated truck, one on the left front of the sedan and one on the left rear of the 

sedan

f) The H. I. Escort for the contaminated truck will carry with him one Watt Meter and the 

respective conversion chart, one Victoreen Gamma Survey Meter and a Radium shielded 

standard. The Watt meter is to be adjusted to a zero reading in any convenient non-active 

area and carefully calibrated with the shielded radium source. 
Rev 00, March 29, 2012 Page 12 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

1948

Kenney, W. K., Memorandum dated February 28, 1948 to J. F. Tribby, entitled “Analysis of 

Beta, Gamma Radiation Exposure of Sigma Building Personnel,” Los Alamos National 

Laboratory, Los Alamos, NM, [SRDB Ref ID: 8181, p 43]

Brass film badges were issue to all Sigma and RT personnel October 20, 1947 in order to 

maintain a complete record of the exposure of the people in that area to beta, and gamma 

radiation. They have been changed and reissued every two weeks since that time. The 

following persons have received at least one exposure reading of over 0.290 roentgen for a two 

week period (over one quarter of an average tolerance dose, 0.1 r/day – gamma, 0.1 rep/day –

beta, or beta, gamma). [List of workers follows]

Hardy, H. L., Memorandum dated June 7, 1948 to H. Whipple, entitled “Film Badges – DP 

East,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8181, p 51]

This memorandum provides an explanation as to why DP East workers were not wearing their 

film badges. It was stated that the workers stopped wearing the film badges in the spring of 

1947 after a trial period of three months which showed no measureable exposure whatsoever. 

Plastic wrist badges are worn at times. The question is posed as to the merit to persuade the 

DP East personnel to wear film badges routinely regardless of past negative dose results. 

Whipple, H. O., Memorandum dated June 8, 1948 to H. L. Hardy, entitled “Film Badges – DP 

East,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8181, p 52]

The memorandum contains an analysis of DP east exposures. A three month study of 

exposure to workers at DP East working with polonium sources showed very low exposure from 

gamma radiation in comparison to their alpha activity. Expected doses would actually be lessthan natural background exposures. The worst workplace exposure occurs in the vault. It 

would require Po of about 2,000 Ci to result in an 8-hour day tolerance dose. It was suggested 

that if this much Po was in the vault then consideration should be given to requiring badges to 

be worn.

Anonymous, 1948, Group CMR-12 Progress Report, Health and Contamination, July 20 -

August 20, 1948, Los Alamos National Laboratory, Los Alamos, NM August 14, [SRDB 

Ref Id: 13465]

Photographic Dosimetry. During the month, 694 films were developed servicing 627 brass 

badges. Results were read on the Weston Photographic Analyzer and recorded. It was 

necessary to read the DuPont film in only two cases. One was the high reading mentioned 

below; the other was due to a lost film. In addition to the brass badges worn on the body, 67 

plastic wrist badges were processed. Each film emulsion in both plastic and brass holders was 

calibrated using gamma radiation from a 0.5 mm platinum shielded, radium source in 
Rev 00, March 29, 2012 Page 13 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

equilibrium with its decay products. A 100 millicurie source is used for the Eastman Type K film 

(accurate to approximately 3 Roentgens) and a 500, millicurie source was used for the DuPont 

type D-2 film (covering from 2 to 30 roentgens). For the exposures reported, 576 were worn by 

personnel and 43 were planted in various locations. Twelve badges, including wristlets, were 

planted in the various badge storage racks as blanks. The average personnel exposure, 

neglecting one high reading, was 0.004 roentgens per week; the average exposure for the 

planted badges was 0.185 roentgen per week. The maximum rack blank reading for a two 

week period was 0.003 roentgen.

1949

U.S. Department of Energy, 1997, Linking Legacies, Office of Environmental Management, US 

Department of Energy, Washington, D.C., [SRDB Ref ID: 11930]

LANL was the lead site for U.S. nuclear component fabrication until 1949, when the Hanford 

Plutonium Finishing Plant in Washington began making pits, the central cores of the primary 

stages of nuclear devices. 

Littlejohn, 1949, Memorandum dated January 10, 1949 to staff entitled “Method of Reporting 

Beta Exposures on Personnel Exposure Reports,” Los Alamos National Laboratory, Los 

Alamos, NM, [SRDB Ref ID: 8181, p 57]

Changes in the LANL film dosimeter were recently made which allow separate determination of 

the beta and gamma dose. The change consists of a film packet inserted in a brass clip that 

provides only partial shielding of the film surface. The brass thickness used is sufficient to 

absorb almost all beta radiation present while having negligible effect on the gamma intensities. 

By a comparison of the film densities under brass with those not under brass, a separate 

evaluation of the beta exposure received can be made. 

1951

Littlejohn, 1960, Photodosimetry Procedures at Los Alamos, LA-2494, Los Alamos National 

Laboratory, Los Alamos, NM, August, [SRDB Ref ID: 951] 

This reference provides some historical information as follows: “The Los Alamos Scientific 

Laboratory film badge in use today (i.e., 1962) has remained unmodified since its inception and 

adoption in 1951.” The dosimeter included a body film-badge dosimeter using Du Pont 502 

dental film and utilizing a 20 mil cadmium filter, a 20 mil brass filter, and an unshielded area.

Storm, E.,, 1951, The Response of Film to X-Radiation of Energy up to 10 MeV, LA-1220, Los 

Alamos Scientific Laboratory, Los Alamos, NM, March 22, [SRDB Ref ID: 978]

The response of Eastman Kodak type K and DuPont 552 film to high energy x-rays was 

investigated. The densities on the unfiltered portion of the DuPont film and those under the 

brass and cadmium filters are very nearly identical from 0.3 to 2.0 MeV, beyond which point the 

brass and cadmium densities become slightly greater. For a given roentgen (R) value, a greater 
Rev 00, March 29, 2012 Page 14 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

response in terms of density is obtained on the film as the effective energy is increased beyond 

2.0 MeV. A method of determining the effective energy by means of an additional lead filter on 

the film is described. When a film is exposed to beta radiation in addition to photon radiation, 

the probit density under the brass minus the probit density under the lead can be used to 

determine the effective energy due to the photon radiation. The exposure is then found from the 

calibration curve made with this energy. Any increment in density on the unfiltered film above 

that due to the photon radiation is attributed to beta radiation.

Storm, E., G. M. Angleton, and G. H. Pettengill, 1951, The Response of Sensitive 552 DuPont 

Film to Beta Radiation, LA-1284, Los Alamos Scientific Laboratory, Los Alamos, NM, 

August 13, [SRDB Ref ID: 976]

This reference is a technical report concerning the response to beta radiation of sensitive 552 

DuPont film, enclosed in the usual manufacturer's packet, was measured in terms of rep. Seven 

beta emitting isotopes covering a maximum energy range from 0.26 to 3.50 MeV were used. 

The exposures were measured in rep by means of an air ionization extrapolation chamber. For 

each source, thirteen different exposures were made covering a range from 0.1 to 5.0 rep, three 

separate films being run for each specific exposure. A 30 me/em2 cellulose acetate filter was 

placed over the end of each film, and the calibration curves obtained under the filtered and 

unfiltered portions of

the film. The film response was found to diminish sharply below 0.8 MeV, and become nearly 

energy independent beyond 2.5 MeV. A method for determining both the energy and the 

exposure of a film exposed to gamma and beta radiation is described in the report.

1952

The first edition of the LANL "General Handbook for Radiation Monitoring" was prepared in 

1952 by Robert F. Barker (Healy 1970, SRDB 943)

1953

1954 

Barker, R. F., 1954, “General Handbook for Radiation Monitoring,” LA-1835, Los Alamos 

National Laboratory, Los Alamos, NM, [SRDB Ref ID: 968]

This document was written specifically for use at Los Alamos. Each individual at the Los 

Alamos National Laboratory who has contact with radioactive materials or radiation is 

responsible for: 

1. Keeping his own exposure to radiation as well as that of others as low as possible and 

specifically below the maximum permissible levels of 300 mr for gamma or 500 mrep for 

beta plus gamma radiation per week except in case of extreme emergency or exposure 

incurred during medical examinations and treatments. Health Division approval should 
Rev 00, March 29, 2012 Page 15 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

be sought in advance for other urgent situations requiring exposures in excess of the 

above values.

2. Wearing the prescribed monitoring equipment (pocket dosimeters, film badges) in 

gamma, beta, and neutron radiation areas. Requesting neutron film badges where 

significant neutron exposures are anticipated. Surveying hands, shoes and body for 

radioactivity and removing loose contamination to the tolerance levels before leaving the 

Laboratory, in accordance with the recommended decontamination procedures.

3. Wearing appropriate protective clothing whenever clothing contamination is possible,

and not wearing such clothing outside of the Laboratory area. Using gloves, hoods, and 

respiratory protection (respirators or supplied air masks as recommended by the Health 

Division) where necessary. Using proper techniques and facilities in operations

involving radioactive or toxic materials. 

Total Body Exposure

Xrays and gamma rays 300 mr per week

Beta 500 mrep per week

Beta and Gamma 500 mrep per week

Xray (below 15- kev average) 500 mr per week

The maximum permissible exposure for neutrons, as adopted at the Tripartite Conference in 

Harriman, New York, April 1953, (NBS Handbook 55) varies with energy. 

1955

Kalil, F., 1955, A Film-Badge Method of Differential Measurement of Combined ThermalNeutron and Gamma-Radiation Exposures, LA-1923, Los Alamos National Laboratory, 

Los Alamos, NM, [SRDB Ref ID: 964]

A body film-badge dosimeter using Du Pont 502 dental film and utilizing a 20 mil cadmium filter, 

a 20 mil brass filter, and an unshielded area was calibrated by exposure to combinations of 

thermal neutrons and gamma radiations from the thermal column of a homogeneous reactor 

and a radium source. A method was devised whereby combined thermal neutron and gammaradiation exposures can be differentiated and evaluated. The method of differentiating and 

evaluating the thermal-neutron exposure is accurate, provided the gamma ray energy spectrum 

lies between 0.15 and 10 MeV. The gamma radiation exposure can be accurately evaluated, 

provided the gamma-ray energy lies between 0.3 and 3 MeV, a range over which the film-badge 

response is independent of the gamma ray energy. Beta-ray exposures, under restricted 

conditions, can also be roughly evaluated by previously established techniques.

1956
Rev 00, March 29, 2012 Page 16 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Anonymous, 1956, Procedure entitled “Modification of Nuclear Track Plate Evaluation 

Procedure,”, Los Alamos National Laboratory, Los Alamos, NM., November 1, [SRDB 

Ref ID: 8181, p 231]

This reference describes changes in the nuclear track plat evaluation procedures that went into 

effect shortly after 11/1/1956. The fact of recording exposures of less than 10% as zero 

exposure was started with the third quarter of 1956 (i.e., NTPs pertaining to the month of July 

and thereafter). The step by step NTP evaluation procedure follows.

1957

Anonymous, 1957, Procedure entitled “Changes in Certain Portions of Permanent Personnel 

Exposure Record of LASL Personnel,”, Los Alamos National Laboratory, Los Alamos, 

NM., April 3, [SRDB Ref ID: 8181, p 233]

Plans are underway to transcribe all permanent radiation exposure records of LASL personnel 

to an IBM system which requires certain changes prior to the changeover. 

Meyer, D. D.., LANL, Letter to A. R. Keene, Hanford, dated March 12, 1957 concerning policies 

for personnel with plutonium intakes, Los Alamos Scientific Laboratory, Los Alamos, NM, 

[SRDB Ref ID: 37969] 

Current plutonium in urine assay capabilities are such that establishing body burdens les-than 

the maximum permissible limit (0.04 μC) cannot be done with any degree of accuracy. For 

situations where personnel have intakes of 100% or more of the maximum permissible limit, 

personnel work assignments are restricted from intimately working with plutonium solutions, 

powders, or metal though sealed-hood gloves or in ventilated laboratory hoods. These persons 

are assigned to further plutonium work in operating locations where the risk of further exposure 

to plutonium would require a major plant accident. 

1958

Dummer, J. E. Jr., 1958, "General Handbook for Radiation Monitoring," LA-1835 3rd Edition, Los 

Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 967]

1959

1960

Los Alamos Dosimetry, “Photodosimetry Evaluation Book "Bible" Volume II Procedures 1960-

69,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8173]
Rev 00, March 29, 2012 Page 17 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

This reference contains many documents describing the Los Alamos dosimetry system, 

calibration, and dose assessment.

(LASL 1969)

As of April 1960, the brass-cadmium film badge was being worn by about half of University of 

California employees, all of the Security Force, and 75% of Zia employees. At most sites, film 

badges were reportedly issued "only to personnel who need them." The stated plan was to 

combine the film badge with the site security badge to increase compliance with the requirement 

to wear dosimeter badges, and it was proposed that badges be issued to all LANL and AEC 

personnel on a regular basis. As of 1960, the following external radiation dose data were 

recorded (Littlejohn 1961):

 Gamma dose (rem)

 Beta dose (rad)

 Thermal neutron dose (from cadmium optical density minus brass optical density, rem)

 Fast neutron dose (from NTA film, rem)

Littlejohn, 1960, Photodosimetry Procedures at Los Alamos, LA-2494, Los Alamos National 

Laboratory, Los Alamos, NM, August, [SRDB Ref ID: 951] 

The Los Alamos Scientific Laboratory film badge in use today has remained unmodified since its 

inception and adoption in 1951. It has, however, become more versatile than its original 

counterpart by the inclusion of a high-range-gamma, fast-neutron film packet. Subsequent 

experimentation has also enabled the badge to be used in the detection and measurement of 

thermal neutrons. For routine personnel monitoring, the LASL badge utilizes two film packets: 

the DuPont 543 and the Eastman Experimental Personnel Neutron Monitoring Film Type B.

1961

Storm, E., and S. Shlaer, 1961, The Development of Film Badges Containing Multi-element 

Filters to Reduce the X-ray Energy Dependence of Photographic Film, LA-3001, Los 

Alamos National Laboratory, Los Alamos, NM, July [SRDB Ref ID: 947]

This report describes the experimental work leading to the development of flat roentgen 

response film badges containing multi-element filters. The films were exposed to fluorescent x 

rays from 30 to 100 keV, heavily filtered direct x-ray beams from 100 to 250 keV, and isotope 

gamma rays from 250 to 1250 keV. Measurements showed that the unfiltered response of 

personnel films was 15 to 30 times greater to 40 keV x rays than to 1250 keV gamma rays. 

Calculations indicated that a filter consisting of several elements with K-edges evenly spaced 

from 40 to 90 key could reduce the energy dependence of the film to within acceptable limits. 

Such multi-element filters were placed in cycolac plastic film badges. It was necessary to place 

copper between the multi-element filter and the film to reduce the effects of fluorescent radiation 

produced in the filter. Measurements made with low energy radiation showed that the film 

blackening behind the filter was due primarily to radiation scattering in the plastic and not to 
Rev 00, March 29, 2012 Page 18 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

radiation passing directly through the filter. Two plastic film badges were developed with either 

lead frames or lead lattices placed around the filters to reduce the amount of radiation scattering 

into the filtered area.

The lead-frame badge contains a multi-element filter (gadolinium, erbium, tantalum, gold, and 

bismuth) and a 0.02 in. thick copper filter; the response of DuPont 502, DuPont 508, DuPont 

555, Eastman Type II, and Ilford PM-l film in this badge is flat within 30 per cent from 40 to 1250 

keV; the badge is directionally independent within 30 per cent over this energy region, but the 

density under the filtered area at low energies is non-uniform, the edges being darker than the 

central region. The lead-lattice badge contains a multi-element filter (Same elements as in the 

frame badge, but in different proportions) and a copper filter whose thickness varies with the 

film type; the response

of the same films listed above is flat within 30 per cent from 50 to 1250 keV; it is directionally 

dependent at low energies, and the density under the filtered area is uniform 

The badges were modified to permit the evaluation of thermal neutron and beta radiation; these 

modifications did not affect the photon film response of the lattice badge, but the frame badge 

was now directionally dependent by as much as a factor of 3 because of the reduced size of the 

filters. A method of measuring thermal neutrons was devised using two multi-element filters 

having similar photon responses; one filter containing gadolinium gave a Co-60 gamma ray to 

thermal neutron exposure ratio of 1.43 R/rem, and a second filter containing molybdenum 

instead of gadolinium gave a ratio of 0.70 rem. The film badge response on a phantom was 

higher than in air by a factor of 1.56. An estimate was made of the accuracy of the gamma 

exposure evaluation when the film is exposed to both gamma and fast neutron radiation; film 

badges exposed to the Godiva critical assembly read 70 per cent higher than glass dosimeter 

rods exposed at the same time and in the same location.

1962

1963

Dummer, J. E., Memorandum to D. D. Meyer dated March 3, 1963 entitled “Correlation between 

Brass-Cadmium and Cycolac Film Badges,” Los Alamos National Laboratory, Los 

Alamos, NM, [SRDB Ref ID: 8173, p 63]

Beginning in October 1962, the new multi-element filter film badge (hereafter referred to as the 

cycolac badge) was issued to about 100 persons who had a history of appreciable or out of the 

ordinary radiation exposure. After a month’s use, one user at the DP West plutonium facility 

appeared to be receiving considerably more exposure than had been measured with the old 

badge (hereafter referred to as the brass-cadmium badge). An investigation was initiated to 

examine the cause. 
Rev 00, March 29, 2012 Page 19 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

The radiation in the workplace is stated to be:

Percentage Photon Energy, keV

65 – 70 L X-rays (~17 keV) + 26 

10 – 20 60 

1 – 10 100 

~0 - 7 >200 

The investigation showed that the cycolac badge measures the dose correctly within ±10% 

when the source is unfiltered. When filtered by glass or steel, the hard component is measured 

correctly but the soft component is overestimated, making the total dose in error by as much as 

60%. The brass-cadmium badge underestimates the dose by a factor of 2 in the unfiltered 

cases and a factor of 3 in the filtered cases. Considering there is no way to know whether 

badges worn at DP are exposed to a “filtered” or “unfiltered” source, the badges must be 

interpreted as if “unfiltered” when potential sources of soft radiation exist. 

Hankins, D. E., 1963, Monitoring Intermediate Energy Neutrons, Health Phys., Vol. 9, pp. 31-39.

This paper describes intermediate-energy neutron monitoring techniques studied at the Los 

Alamos National Laboratory. A recently developed instrument for simultaneously monitoring 

neutrons with energies from thermal to 7 MeV is discussed. Experimental data obtained using 

several instruments and techniques with various neutron spectra are compared. The relative 

dose rates of thermal, intermediate, and fast neutrons under various shielding conditions are 

presented, and the techniques for monitoring intermediate energy neutrons are evaluated.

Hankins, D. E., Letter to distribution dated August 28, 1963, entitled “NTA Film Badge 

Response to PuF4 Neutrons,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB 

Ref ID: 22660]

This reference contains the dose results for an eva1uation of the NTA neutron film response to 

PuF4 neutrons at Building 501, DP West. The results of ten film badge exposures are provided 

in the letter. An area of ten (10) mm was used to read the number of tracks for each film 

instead of the one (1) mm normally read for personnel exposures. As noted in the reference a 

deviation of about a factor of 2 was observed in the number of tracks/film. The neutron source 

strength was measured with one of the 10" portable units and is probably accurate to ±20%. 

The average mrem/track value of about 16 is considerably less than the 80 mrem/track found in 

a previous study. As a result of the above, it is recommended in this reference that 15 or 16 

mrem/track be used in the future to evaluate personnel films.

1964

AEC, Immediate Action Directive, dated February 17, 1964, entitled “Posting Requirement for 

Contractors – Radiation Protection Standards,” [SRDB Ref ID: 1287] 
Rev 00, March 29, 2012 Page 20 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Effective upon receipt of this directive, AEC contractors are required to post copies of the 

following notice at a location or locations in such plants or facilities where it can be readily 

viewed by the contractor’s employees.

NOTICE TO EMPOLOYEES

U. S. ATOMIC ENERGY COMMISSION’S

STANDARDS FOR PROTECTION AGAINST 

RADIATION

Standards for protection of employees against radiation 

are established by

the Atomic Energy Commission. These standards 

cover:

a) Measuring, recording and 

reporting to employees and the 

AEC the amount of radiation 

received by employees in the 

performance of their work.

b) Monitoring and controlling the 

handling and use of radioactive 

material in the plants, and the 

discharging of radioactive 

materials to the environment 

outside of the plants.

c) Other matters dealing with the 

control of possible hazards that 

might result from the handling 

or use of radioactive materials 

in all AEC facilities.

REPORTS ON EMPLOYEE RADIATION EXPOSURE 

HISTORY

Your employer is required to establish procedures to 

assure that employees are:

1. Advised, upon written request, 

of their occupational radiation 

exposure as indicated in the 

exposure record.

2. Notified immediately of any 

radiation exposure which 

exceeds the limits specified by 
Rev 00, March 29, 2012 Page 21 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

the AEC’s standards.

3. Provided, at the time of or after 

their terminations, upon 

request and within forty-five 

days after the request, with a 

written summary of their 

cumulative recorded 

occupational radiation 

exposures received during the 

period of employment.

POSTING

Your employer is required to post, or otherwise make 

available to you, a copy of AEC radiation protection 

standards, and the approved operating procedures 

relating to radiation protection applicable to the work in 

which you are engaged.

YOUR RESPONSIBILITY AS A WORKER

You should familiarize yourself with those provisions of 

the AEC standards for radiation protection and the 

operating procedures applicable to your work. You 

should observe their provisions for your own protection 

and that of your fellow workers.

AEC, Immediate Action Directive, dated March 3, 1964, entitled “Notice to Employees,” [SRDB 

Ref ID: 1287] 

Further information similar to the forgoing posting but to include a section as follows;

Reports on Employee Radiation Exposure History

Your employer is required to establish procedures to assure that employees are:

1. Advised, upon written request, of their occupational radiation exposure as indicated in 

the exposure record.

2. Notified immediately of any radiation exposure which exceeds the limits specified by the 

AEC’s standards.

3. Provided, at the time of or after their terminations, upon request and within forty-five 

days after the request, with a written summary of their cumulative recorded occupational 

radiation exposures received during the period of employment.
Rev 00, March 29, 2012 Page 22 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

AEC (Atomic Energy Commission), 1964, Radiation Protection Standards, Form AEC-9 with 

Note No. 1 and Note. No. 2. Atomic Energy Commission, [SRDB Ref ID: 1287].

A. Radiation from sources external to the body.

Type of Exposure Period of Time Dose 

(rem)

Whole body, head and 

trunk, active blood forming 

organs, gonads, or lens of 

eye

Accumulated 

dose 

Calendar Quarter

5 (N-18)

3

Skin of whole body and 

thyroid

Year 

Calendar Quarter

30

10

Hands, and forearms, feet 

and ankles

Year 

Calendar Quarter

75

25

AEC assigned weapon surveillance and repair mission to Pantex, while both Pantex and 

Burlington shared the retrofits and modifications mission. 

1965

1966

1967

Hankins, D. E., 1969, The Response of Selected Neutron Monitoring Instruments to Several 

Types of Neutron Sources, Health Phys., Vol. 13, pp. 587-592.

This paper compares the response of several neutron-monitoring instruments in use at Los 

Alamos to nine neutron sources and concludes that differences in the neutron spectra of the 

sources and differences in the energy dependence of the instruments significantly affect 

calibration results. Neutron sources of 238PuBe, 239PuBe, AmBe, PoBe, RaBe and spontaneous 

fissioning 244Cm were used. The sources were calibrated in the Los Alamos Scientific 

Laboratory’s standard pile with a probable error of ±5 per cent for the reported absolute source 

strength, and a probable error of ±3 per cent for the comparison made in this study. The 

instruments used were the Hurst absolute fast-neutron dosimeter, the Ludlum Model 11 neutron 

detector, the Eberline Portable Neutron Counter (PNC), The Eberline Fast-Neutron Detector 

(FNIA) (Scintillator), the 10-inch, single sphere neutron-monitoring instrument, and the 8-, 3-

and 2-inch spheres of the multisphere technique. The results indicate that all the instruments 

have essentially the same response to the 238PuBe, AmBe, and PoBe neutron sources. The 

moderated BF3 instruments have a high response (~14 per cent) to the 239PuBe and RaBe 

sources, and a high response (~38 per cent) to the 244Cm. The fast-neutron scintillator had a 

response 58 per cent low to the 244Cm. More results are shown in the paper. 

1968
Rev 00, March 29, 2012 Page 23 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Group HS-1, 1968, The New LASL Film Badge and Neutron Dosimetry Packet, LA-3889, Los 

Alamos National Laboratory, Los Alamos, NM, January [SRDB Ref ID: 35008] 

This is a basic document apparently provided to all employees at LASL (see Jalbert 1974 letter) 

describing the implementation of the new Cycolac plastic dosimeter which contains multielement filters, two film packets, and identification plates. The two film packets used with the 

LASL film badge are the DuPont Type 545 Dosimeter Film pack and the Kodak Personal 

Neutron Monitoring Film Type B pack. The DuPont pack contains a single gamma-sensitive film 

of type 555 emulsion in a light-tight wrapping. This film is used to measure the monthly 

exposures to x rays or beta, gamma, and thermal neutron radiation. The useful range is 

approximately 0.03 to 10 rem. The Kodak film packet contains gamma-insensitive film, a 

nuclear track film, and two thin aluminum absorbers in a light-tight wrapping. The gamma 

insensitive film has a useful range from about 10 to 1,000 rem. The nuclear track film (Kodak 

NTA) is used in conjunction with aluminum absorbers to measure fast neutron exposures from 

about 0.03 to 10 rem. Processing NTA film is a time-consuming activity, requiring a minimum of 

six minutes per film as compared with a half minute for determining the density in the three filter 

areas of the DuPont film. Neither personnel nor facilities permit the H-1 Photodosimetry Section 

to analyze all the NTA films which are issued; however, all issued NTA films are developed and 

stored. In many laboratory areas a detectable number of fast neutrons does not exist, and the 

NTA films worn in these areas are not evaluated. In general, only those NTA films worn by 

persons suspected of having received significant fast neutron exposure are evaluated; these are 

approximately 10% of all NTA films issued. 

The PND neutron packet consists of a bare indium foil, a cadmium-covered indium foil, a 

cadmium-covered copper foil, and a sulfur pellet, all encased in a clear plastic wafer. When 

these packets are exposed to a spectrum of neutrons, several activities are induced in the foils. 

Upon counting the foils and pellet, the rad dose of the neutron exposure may be estimated in 

several neutron–energy bands.

Hankins, D. E., A Study of Selected Criticality-Dosimetry Methods, LA-3910, Los Alamos 

National Laboratory, Los Alamos, NM {SRDB Ref ID: 27248]

This reference describes several methods for determining the dose received by persons 

accidentally exposed to a criticality excursion. The dosimetry methods included use of film 

badges, thermoluminescent dosimeters, threshold detector units, Hurst proportional neutron 

counters, 10-in.-sphere neutron detectors, the multisphere technique, blood sodium activation, 

and Geiger counter readings at the abdomen. Five critical assemblies with leakage spectra 

varying from a fast neutron spectrum to a highly moderated spectrum were studied. The effects 

of distance from the assembly, room scatter, shielding, and assembly height above the floor 

were investigated. The results indicate that considerable information must be available before 

an accurate assessment of a person's dose can be made. If no information about the accident is 

available, dosimetry using a ratio of the hair and blood-sodium activation will give the dose to 

within ±20 to 30% except where massive uranium or iron shielding occurs.
Rev 00, March 29, 2012 Page 24 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

1969

Vallario, E. J., D. E. Hankins, and C. M. Unruh, “AEC Workshop on Personnel Neutron 

Dosimetry, September 23-24, 1969,” BNWL-1340, Pacific Northwest Laboratory, 

Richland, WA [SRDB Ref ID: 11096]

This was the first of a series of AEC/DOE workshops that focused on methods of personnel 

neutron dosimetry. AEC laboratory and contractor representatives from ten sites presented 

summary reports of personnel neutron dosimetry methods at their respective sites. Since there 

is no personnel neutron monitoring system for all neutron energies, a summary description of 

several techniques is provided such as neutron to gamma ration, rem dose meter, etc. Most 

sites have relied upon nuclear track emulsion type A (NTA) film to measure fast neutron dose 

which under adequately controlled conditions and appropriate calibration may be entirely 

satisfactory. The document summary states that “There are several acceptable thermal neutron 

monitoring dosimeters available and in general use. Under proper conditions the NTA film can 

provide reliable and satisfactory fast neutron dose equivalent monitoring. Several laboratories 

are using NTA film to good advantage for fast neutron dosimetry. For the intermediate neutron 

exposure around reactor facilities and for the moderated fast energy neutron sources NTA 

personnel neutron dosimeters cannot be effectively used. This leaves a major gap in the 

personnel dosimetry program which at many installations may be quite serious. New 

approaches, methods, and equipment to improve monitoring for intermediate energy neutrons 

are need and constituted the bulk of discussions at the workshop. 

Hankins, D. E., 1969, “Los Alamos Scientific Laboratory Neutron Dosimetry,” Presented at AEC 

Workshop on Personnel Neutron Dosimetry, September 23-24, 1969, BNWL-1340, 

Pacific Northwest Laboratory, Richland, WA [SRDB Ref ID: 11096]

Four methods of personnel neutron dosimeter development have been investigated at Los 

Alamos as follows:

1. Direct response of TLD detectors to fast neutrons

2. Fission fragment tracks in solid state devices

3. Use of albedo (reflected) neutrons

4. Activation of metallic foils as described in LA-3910.

Several graphs and tables are contained in this reference.

DS Myers and CT Prevo, 1969, Personnel Dosimetry Associated with the Handling of a Large 

Numbers of 3 Kg 239Pu Billets, Lawrence Livermore National Laboratory, Livermore, CA 

[SRDB Ref ID: 53745]

Paper describes process for measuring whole-body neutron doses using a neutron-to-gamma 

dose rate ratio. Since the neutron-to-gamma dose rate ratio is dependent upon the size, 
Rev 00, March 29, 2012 Page 25 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

spacing, and moderation of the array, a new ratio is determined for each array. A neutron-togamma dose ratio was also established for billet surface radiation using computer techniques. 

The neutron dose is then established by applying the measured neutron-to-gamma ratio to the 

whole-body gamma dose as measured by the film badge, and to the gamma hand dose as 

measured by thermoluminescent dosimeters. The monthly neutron-to-gamma dose ratio 

ranged from 2 to 5 and the hand dose was about a factor of 2 greater than the whole body dose. 

1970

Healy, J. W., 1970, Los Alamos Handbook of Radiation Monitoring, LA-4400, Los Alamos 

National Laboratory, Los Alamos, NM, [SRDB Ref ID: 943]

The first edition of the LANL "General Handbook for Radiation Monitoring" was prepared in 

1952 by Robert F. Barker to provide basic information for members of the Monitoring

Group at the Los Alamos National Laboratory. A second edition was prepared by Barker in 

1954 for updating and to remove a few local terms that were cryptic to the large audience the 

book had attracted. A third edition, compiled by Jerome E. Dummer, Jr., was issued in 1958. 

This handbook contains substantial information regarding radiation safety regulations, 

workplace monitoring, instruments, etc. It is stated that “the policy of the LANL is that exposure 

of individuals to radiation shall be kept to a minimum commensurate with the needs of the work 

and should not exceed the maximum permissible values recommended by the National Council 

on Radiation Protection and Measurements and prescribed by AEC Manual Chapters 0524 and 

0502 and appendices.” The specific assignments of the Health Physics Group (H-1) within the 

Health Division include:

 Consult on all aspects of radiation protection.

 Maintain routine surveillance of all radiation or contamination areas.

 Issue and maintain reports on personnel monitoring.

 Review and monitor all shipments of radioactive materials.

 Provide limited decontamination service for large or expensive items.

 Routinely test all encapsulated sources and provide a facility for storage of unused 

encapsulated sources.

 Review and approve all operating procedures involving use of radioactive materials.

 Collect and interpret data from supplementary programs such as bioassay, whole-body 

counting, or wound counting.

 Supervise disposal of solid wastes.

This document contains substantial information such as methods for monitoring for beta/gamma 

and neutron radiation; and capabilities of instruments in use at LANL.

US Atomic Energy Commission, Albuquerque Office, 1970, “Annual Summary of Whole Body 

Radiation Exposures to External Penetrating Radiation Accumulated During 1969,” Los 

Alamos National Laboratory, Los Alamos, NM, February 9, [SRDB Ref ID: 13800]
Rev 00, March 29, 2012 Page 26 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

This document concerns annual statistical dose data reported to the AEC REIRS system for 

calendar year 1969. The data for LANL organizations are shown in the following:

Organization

Total not

monitored

No. of annual doses (rem) in each 

category

Total

Monitored

0-1 1-2 2-3 3-4 4-5 5-6

LANL 1,897 2,624 43 27 7 6 4 2,711

Zia Company 219 840 1 0 0 0 0 841

AEC/AL 29 306 3 2 1 0 0 312

Visitors 6,397 559 0 0 0 0 0 559

1971

US Atomic Energy Commission, Albuquerque Office, 1971, “Annual Summary of Whole Body 

Radiation Exposures to External Penetrating Radiation Accumulated During 1970,” Los 

Alamos National Laboratory, Los Alamos, NM, February 9, [SRDB Ref ID: 13801]

This document concerns annual statistical dose data reported to the AEC REIRS system for 

calendar year 1970. The data for LANL organizations are shown in the following:

Organization

Total not 

monitored

No. of annual doses (rem) in each 

category

Total

Monitored

0-1 1-2 2-3 3-4 4-5 >5

LANL 1,736 2,507 57 17 18 16 6 2,621

6,630 663 0 0 0 0 0 663

Zia Company 140 907 0 0 0 0 0 907

2,250 0 0 0 0 0 0 0

Johnson, L., Memorandum to JNP Lawrence, dated July 1, 1971, entitled “NTA Fading at DP,” 

Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8176]

This reference describes three studies of NTA fading in the workplace. Radiation survey results 

at DP for both gamma and neutron radiation indicate a higher proportion of neutron radiation 

than shown in the measured film doses. The results were interpreted as indicating possible 

significant NTA fading at both two and four weeks development delay times (i.e., Table III, Time 

of NTA development following exposure, mean NTA response at: 6 hrs – 1.62, 2 weeks – 1.42, 

4 weeks – 0.97) . No significant gamma film fading was observed. The neutron energy 

spectrum was measured in the 3rd workplace study during June 1971 using the multisphere 

technique. The average neutron energy was in the range of 1.0 to 1.25 MeV. There is a handwritten note on the memo to the effect that the calibration factor for NTA film to be used for DP 

only would be changed to 0.024 rem/track effective July 1971. 
Rev 00, March 29, 2012 Page 27 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Vallario, E. J., D. E. Hankins, and C. M. Unruh, “Second AEC Workshop on Personnel Neutron 

Dosimetry, July 8-9, 1971,” BNWL-1616, Pacific Northwest Laboratory, Richland, WA 

[SRDB Ref ID: 78604]

This was the second AEC workshop to focus on methods of personnel neutron dosimetry 

following the first workshop help approximately two-years previously. Neutron dosimeters 

utilizing the Albedo neutrons were described by representatives from several facilities within the 

reference. The albedo systems require a fixed or generally well known spacing between the 

dosimeter and the body of the individual. Usually direct contact is recommended. Energy 

dependence is still an important problem, but the dosimeters can give good results when 

properly worn and when calibrated with neutron spectra approximating those to which they will 

be exposed.

Littlejohn, G. J., Memorandum to Personnel Dosimetry Staff, dated July 8, 1971, entitled “NTA 

Fading at DP,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8176]

This memorandum notes the L. Johnson (1971) study findings and documents the change in 

NTA calibration from 0.016 rem/track to 0.024 rem/track for DP West personnel beginning with 

the July 1971 dosimeter issue. 

Johnson, L., Memorandum to File, dated July 9, 1971, entitled “NTA Fading at DP,” Los Alamos 

National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8176]

This memorandum describes at study of film versus thermoluminescent dosimeter (TLD) 

components in that beginning in September 1970 selected individuals at DP were issued film 

badges modified to receive a TLD ribbon-containing plastic insert. Each badge insert had one 

TLD-600 and one TLD-700 ribbon placed in it. The primary purpose for the modified badges 

was to estimate individual exposures during the period between film development and 

evaluation. As noted in this memorandum and attached tables, the TLD component showed 

significant values for persons working in 238Pu areas due, as noted in the memo, to intermediate 

energy neutrons. The varying amounts of neutron shielding materials in the 238Pu areas 

provides a larger proportion of intermediate energy neutrons than in the 239Pu handling areas. 

The results of this study are stated to illustrate the complexity of neutron dosimetry with TLDs 

under circumstances where the neutron-energy spectrum is variable and greater or lesser 

amounts of gamma ray component are present.

Johnson, L. J., Memorandum to J. N. P. Lawrence, dated November 11, 1971, entitled 

“Recommendations for assignment of Neutron Exposure Dose to Extremities,” Los 

Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8176]

This reference describes an evaluation of neutron dose to the extremities using TLDs and NTA. 

As noted in the memorandum, there was no reasonable means available to routinely measure 

neutron dose to the extremities. In the past, no neutron exposure dose to the hands was taken 
Rev 00, March 29, 2012 Page 28 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

into account. This memorandum recommends that a neutron exposure dose equal to the 

gamma exposure dose as measured by TLD be assigned to those individuals working with 

238Pu, or any high specific alpha activity radionuclide in a low Z compound form. Although there 

is variability inherent to estimating each individual’s extremity neutron dose in this manner, the 

associated uncertainty may be minimized or averaged over the long term. Individuals presently 

working with 239Pu at DP receive a small neutron exposure to the hands compared to the 

gamma exposure and therefore do not need special extremity neutron dose assignment. 

Johnson, L. J., Memorandum to W. J. Maraman, dated December 3, 1971, entitled “Neutron 

Hand Exposure Dose Assignment,” Los Alamos National Laboratory, Los Alamos, NM, 

[SRDB Ref ID: 8176]

This memorandum formalizes implementation of assignment of a neutron exposure dose equal 

to the TLD-measured gamma exposure dose beginning January 1, 1972. This only applies to 

individuals handling 238Pu. A review of past hand exposure records indicates that doubling the 

measured gamma dose will significantly effect only 3 or 4 individuals with respect to AEC 

exposure guidelines. The present extremity exposure guidelines, as listed in AECM Appendix 

0524, are 75 rem/yr and 25 rem/calendar quarter. Based on past records, only a few cases 

would have accumulated a total hand exposure approaching these guidelines had a gammaequivalent neutron dose been assigned. This method of assigning neutron exposure doses to 

the hands will not be made retroactive and will be under continuing review to assure proper 

extremity dosimetry.

1972

Hankins, D. E., 1972, "Factors Affecting the Design of Albedo-Neutron Dosimeters Containing 

Lithium Fluoride Thermoluminescent Dosimeters," LA-4832, Los Alamos National 

Laboratory, Los Alamos, NM, January, {SRDB Ref ID: 76956] 

The neutron film packet used in film badges has often proved unsatisfactory for

measurement of the fast neutron dose. Two of the major reasons are that the latent-image track 

fades rapidly where the humidity is high, and the lowest-energy neutrons detectable in routine 

evaluations are ~0.8 to 1.0 MeV. These and several other undesirable features have led many 

organizations to stop using the neutron film. One technique that has been considered to replace 

the neutron film and to measure the dose from lower-energy neutrons is through use of albedoneutron dosimeters.

When the human body is exposed to neutrons, some of the incident neutrons are 

backscattered to create a flux of neutrons of various energies leaving the body. These neutrons 

are called albedo neutrons, and a dosimeter placed on the body to measure this flux of 

backscattered neutrons is called an albedo-neutron dosimeter. Such dosimeters are usually 

designed to detect thermal neutrons, and when cadmium is used to eliminate incident thermal 

neutrons, the dosimeter response is largely from the thermal neutrons that return from the body. 
Rev 00, March 29, 2012 Page 29 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Hankins, D. E., and G. W. Neely, 1972, Correction Factors for 9- and 10-in. Sphere Neutron 

Instruments and 1-in.-dia. Bare BF3 Tubes Used to Monitor Small Beams and Slits, 

Health Phys., Vol. 22, pp. 65-71.

LANL developed 9- and 10-inch sphere neutron survey instruments (remmeters) for use in 

measuring work area neutron doses. Routine practices at LASL showed that these instruments 

were also being used to measure dose rates from small beams and slits in which the sensitive 

volume of the instrument was not uniformly irradiated. This paper provides measured correction 

factors obtained with thermal neutron fields. These factors can be used in many cases to adjust 

the observed reading to a reasonably accurate dose rate. 

Voelz, G. L., 1972, “H-Division Progress Report April through June 1972,” Los Alamos National 

Laboratory, Los Alamos, NM, January, {SRDB Ref ID: 75433]

This reference appears to be a routine progress report. The content of the report includes 

evaluation of health physics issues from throughout LANL facilities. The report describes the 

status of implementation of the LANL thermoluminescent personnel dosimeter and the use of 9-

inch and 3-inch spheres to measure the neutron dose and spectra.

Oak Ridge Associated Universities Team (ORAUT), 2004, “Technical Basis Document for the 

Los Alamos National Laboratory – Site Description,” ORAUT-TKBS-0010-2, National 

Institute for Occupational Safety and Health (NIOSH), Division of Compensation 

Analysis and Support (DCAS), Cincinnati, OH 

Los Alamos Meson Physics Facility (LAMPF) becomes operation during the summer of 1972 as 

the world’s most powerful linear accelerator reaching at full energy generated pulses of 800-

million-volt protons at a repetition rate of up to 120 per second, and an average current of 1 

milliampere. Weapons Neutron Research (WNR) facility, an adjunct to the LAMPF, was built in 

the early 1970s to provide an intense neutron source that could be used to obtain nuclear data 

needed for weapons design. The present day Manuel Lujan, Jr. Neutron Scattering Center 

grew out of the WNR facility. These facilities are key elements of Los Alamos Neutron Science 

Center (LANSCE) research program.

Hankins, D. and J. N. P. Lawrence, Memorandum dated November 9, 1972 to J. Combs, AEC 

OS, Washington, concerning neutron exposure,” Los Alamos National Laboratory, Los 

Alamos, NM, [SRDB Ref ID: 8176]

This reference contains a few notes pertaining to 239Pu and 238Pu workers and apparently the 

accuracy of the recorded total (gamma plus neutron) dose. 

 For 239Pu workers, not in fluoride area, none had high neutron/gamma ratio. The 

observed ratio was 0.7 with a spread from 0.3 to 1.7.

 For 239PU fluoride, data on only one person with a ratio of 2.8 but this person was a 

monitor and not a chemical operator.
Rev 00, March 29, 2012 Page 30 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

The conclusion was stated: ”LANL has at most 3 persons with high neutron to gamma ratio for 

persons working with 239Pu. Appropriate amount of neutron exposure in records already.

 For 238Pu workers, all types, average ratio is 3.9 neutrons/gamma with a range from 2.7 

to 5.5. 

 For 238Pu monitors, average ratio is 3.3 neutron/gamma with a range of 1.9 to 4.6.”

The conclusion was stated: “238Pu exposures began three years ago and appropriate amount of 

neutron exposure in records already.”

1973

H-1 Personnel Dosimetry Section, Memorandum dated January 16, 1973 to H-1 Section 

Leaders, concerning “Evaluation Method Changes,” Los Alamos National Laboratory, 

Los Alamos, NM, [SRDB Ref ID: 8176]

This reference describes the practice for determining the assigned dose. It states “On 

numerous occasions, film badges have not been evaluated correctly. You may or may not be 

aware that a correct evaluation depends on knowing the radiation environment in which the 

badge was worn. That is, was the film badge and wearer exposed to plutonium, x-rays, betas, 

gammas, etc. Quite often, usually through group changes, a person has changed radiation 

environment and the H-1 Personnel Dosimetry Section has not been informed. 

In the future, this information should be supplied to the Personnel Dosimetry Section Office in 

memorandum form for each person requiring a film badge. We are also to be informed as to the 

status of an individual who transfers from one group to another or who works as a casual. This 

information is requested in writing since verbal communication can and has resulted in a 

considerable amount of confusion.”

Maraman, W. J., W. D. McNeese and R. G. Stafford, 1975, “Confinement Facilities for Handling 

Plutonium,” Health Physics, Vol. 29, pp 469-480.

Reference under “Radiation Instrumentation” section states that “neutron survey meters capable 

of detecting fast neutrons were developed in the early 1950s... The first was a modified 

PeeWee for use with a boron-lines probe, 2.5-cm-thick polyethylene moderator and 0.5-mmthick cadmium absorber. This instrument measured in neutron flux (in n/cm2-sec), was 

extremely energy dependent, and correction factors had to be applied for magnitude of flux 

reading and neutron energies. Modified versions of this instrument have been used at DP Site 

up to 1973 when all neutron surveys were performed with a polyethylene sphere rem meter 

which was first developed in the early 1960s at Los Alamos. 

Lawrence, J. N. P., Letter to File, dated May 1, 1973, entitled “Eastman Type II, Open Window 

Factors,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8176]
Rev 00, March 29, 2012 Page 31 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

In evaluating the Cycolac film badge, two constants are required. One is the excessive 

exposure indicated in the open window due to the penetrating exposure recorded under the filter 

and the other is the factor to correct the net exposure under the open window to the delivered 

90Sr/90Y beta exposure. Using 60Co exposures, the ratio of the open window response to the 

filtered area response was determined to be 1.14 with a range from 1.09 to 1.23. Since this was 

not significantly different from the factor (1.17) used for many years, this factor was not 

changed. Badges were exposed to a series of 90Sr/90Y beta exposures from the front and rear 

of the badge. The response of the window was evaluated using a 60Co calibration. The ratio of 

the actual exposure to the evaluation of the open-window area averaged 1.88 for exposures 

from the front and 2.50 for exposures from the rear. The factor used since 1964 is 2.0. Since 

the new factor of 1.88 differs so little from 2.0, and since the film badge has been observed to 

be worn with the rear side forward a significant amount of the time, the old value of 2.0 will be 

retained as the beta calibration factor. 

Lawrence, J. N. P., Letter to File, dated May 1, 1973, entitled “Evaluation Procedure for Cycolac 

Film Badges,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8176]

The last memo on this subject to the photodosimetry historical book, dated November 27, 1963, 

did not discuss two procedures which have been in use since about 1968. One procedure was 

the evaluation method which evaluated only the penetrating x- or gamma-ray exposure, but did 

not evaluate beta or soft x-ray exposure. This method has been used in areas where the 

primary source of exposure was x-ray machines with an effective energy of 40 keV or higher. 

The second procedure was to use the F21 density for the evaluation of gamma exposure, where 

there was no significant thermal-neutron exposure. (The November 27, 1963 memo called for 

the use of F20 density to be used.) Another change which has been incorporated in the late 

sixties was the use of blank fields when no exposure was calculated for that particular type of 

radiation, i.e., when beta was not evaluated, the field was left blank (zeros were not inserted)..

The present computer program used to evaluate Cycolac film badge response uses three 

methods (EVM) designated 1, 4 and 7 as follows:

 EVM-7 is used to evaluate thermal neutrons and penetrating gamma exposures only. 

The same exposure is recorded in the gamma-R and gamma-rem fields, and the beta 

field is left blank (no zeroes). 

 EVM-4 is used to evaluate thermal-neutron, hard-gamma and beta exposures. The 

same exposure is recorded in the gamma-R and gamma-rem fields.

 EVM-1 is used to evaluate exposures to radiations originating from plutonium. In this 

case there is no beta component (and the beta field is left blank), and part of the very 

soft x-radiation does not penetrate to the gonads (and the gamma-R field is larger than 

the gamma-rem field). For EVM-1, the film badge is calibrated against the simulatedplutonium x-ray spectra, described in J. E. Dummer’s memo “Correlation between BrassCadmium and Cycolac Film Badges,” dated March 5, 1963. 
Rev 00, March 29, 2012 Page 32 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Since the March 1963 simulated-plutonium calibration work, an unexpected phenomenon was 

the observation that 60 keV x-rays backscattered from the body to a very significant extent. 

This is particularly important because 1) film has its maximum over-response at about 60 keV 

and 2) 60 keV photons are a significant component of the simulated-plutonium spectra.

Hankins, D. E., 1973, “Neutron Dosimetry Studies at LASL,” Article in AEC 4

th Personnel 

Neutron Dosimetry Workshop, Los Alamos National Laboratory, Los Alamos, NM, June, 

[SRDB Ref ID: 18245]

This article describes a LASL conducted a 6-month comparison study using a simulated TLD 

system and the film badge. The albedo-neutron dosimeters were taped to the bottom of the film 

badges to assure us that both were similarly exposed. In the actual

dosimeter one pair of TLD's would be used but in this study, eight TLD's were placed in the 

albedo-neutron dosimeter and the average reading of the four 6Li and four 7Li TLD's was used. 

Additional TLO's (four compared to two that one would normally use) were placed inside the 

film-badge holder to measure the gamma exposure and thermal-neutrons. The extra TLD's were 

used to study statistical variation one would obtain from the use of fewer TLDs.

The results of the study were rather complex but generally indicated that for the neutron 

component of the dose, reasonable agreement was found in the 238Pu areas. In areas where the 

dose rates were low, <1 mrem/h) the film reported only a small part of the total neutron dose. 

For the total neutron and gamma exposures, we found that an overresponse of the film to lowenergy gamma rays gave a net reported penetrating whole body dose that was approximately 

correct except for one area of the plant where it was high.

Hankins, D. E. 1973, A Small Inexpensive Albedo-Neutron Dosimeter, LA-5261, Los Alamos 

National Laboratory, Los Alamos, NM, July, {SRDB Ref ID: 8081]

This reference describes a small albedo-neutron dosimeter that can be worn by attaching it to 

an existing film badge. The badge is designed to use 6Li and 7Li chips. The dosimeter is very 

energy dependent, having the same energy dependence for fast neutrons as other albedoneutron dosimeters. Workplace calibrations can be determined using the ratio between 9-inch 

rem-meter and a cadmium covered 3-inch sphere. A maximum of eight chips can be placed 

into the dosimeter.

Lawrence, J. N. P., Letter to File, dated December 15, 1973, entitled “Rem/Track Neutron 

Conversion for LAMPF Film Badges,” Los Alamos National Laboratory, Los Alamos, NM, 

[SRDB Ref ID: 8176]

For all laboratory areas except those where plutonium is processed, the standard fast neutron 

dose equivalent for each proton recoil track per square millimeter on a developed NTA film has 

been 8 mrem. This corresponds to a neutron energy of about 4 – 5 MeV. For areas where 
Rev 00, March 29, 2012 Page 33 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

plutonium is processed, it has been determined that the average neutron energy is about 1 

MeV, and the appropriate dose equivalent per track (per square millimeter) is 24 mrem/track.

Using the multisphere technique the neutron energy outside the biological shield at LAMPF, it 

was found that the average neutron energy was 50-100 keV. Since this is closer to the energy 

at DP West than the standard 4 – 5 MeV, it was decided that the 24 mrem/track per square 

millimeter conversion would be used in evaluating LAMPF NTA films. This use of this factor 

became effective for the December 1973 badge issue. 

When LAMPF operations resume on a continuous, predictable basis, a comparison of albedoTLD vs. NTA film exposure study will be conducted to establish experimentally the appropriate 

dose equivalent per track factor.

1974

Lawrence, J. N. P., Letter to PhotoDosimetry Evaluation Book, dated January 23, 1974, entitled 

“Albedo-TLD Versus Film Badge Study for Plutonium-239 Recovery Workers at DP 

West,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 22627]

During the six-month study of the prototype albedo-neutron-TLD versus film badge exposures of 

the DP West in the last half of 1972, the following observations were made:

1. The film badge gamma exceeded that measured by the TLDs. The excess was by a 

factor of 2 for most of the classes of workers at DP West, but was by a factor of 4 for the 

239Pu recovery workers.

2. In general, the film badge fast neutron exposure was only a small (inconsistent) fraction 

of the albedo-neutron-TLD measured exposure.

3. For all of the DP West workers, except the 239Pu recovery workers, the sum of the film 

badge gamma plus neutron exposure was approximately equal to the albedo-neutronTLD gamma plus neutron exposure. However, for the 239Pu recovery worker the film 

badge neutron plus gamma exposure exceeded the albedo-neutron-TLD measurement 

by 1.5

A special X-ray exposure study of the film badge was conducted to determine why the film 

badge would indicate larger exposures than the TLDs.

Lawrence, J. N. P., Letter to J. E. Dummer, dated March 15, 1974, entitled “Personnel Neutron 

Dosimetry for LAMPF Personnel” Los Alamos National Laboratory, Los Alamos, NM, 

[SRDB Ref ID: 8176]

Description of H-1 Personnel Dosimetry practices at LAMPF as follows:
Rev 00, March 29, 2012 Page 34 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

A. For the month of February (January 19 to February 19), H-1 read only one-third of the 

nuclear track (NTA) films issued to MP Division personnel, all films issued to MP Division 

and LAMPF visitor personnel were photographically processed. All films are examined 

for gamma exposure. All films, including the developed nuclear track films, are retained 

permanently. The one-third of the nuclear track films which were read for February are 

those used by personnel whose Group Leaders believe were the most likely to receive a 

detectable exposure.

B. In the event of an eventual lawsuit by a person whose nuclear track films had not been 

read, the nuclear track films for that person would, at that time, be recalled from 

permanent storage and read then.

C. It is readily agreed that neutron exposure is most probable at LAMPF. However, we also 

note that the average energy of the neutrons measured at this time is 200 keV or less. 

Nuclear track films are not capable of measuring neutrons in this energy range. The few 

neutrons which nuclear track films do detect are the high energy tailing of the observed 

average spectrum. To compensate for this lack of sensitivity to neutrons below 800 keV, 

the dose conversion of 0.024 rem per proton recoil track (counted in a one square 

millimeter area) is used. This particular dose conversion is three times larger that that 

used for neutron exposures to 5000 keV neutrons.

D. Nuclear track films are “read” by counting the proton recoil tracks over an area of one 

square millimeter. Using our oil immersion microscopy procedures, the one square 

millimeter area reading is accomplished by counting all tracks within a swath (0.19 

millimeter wide) for a distance of 5.15 millimeters long. This is equivalent to counting the 

tracks in 26.5 microscope fields. Using our TV microscope-pickup procedure, the swath 

is 0.16 millimeters wide and 6.25 millimeters long, which is equivalent to 39 microscope 

fields.

This reference continues further to describe other features of LANL NTA counting procedures.

Lawrence, N. P., Memorandum dated March 15, 1974 to J. E. Dummer, entitled “Personnel 

Neutron Dosimetry for LAMPF Personnel,” Los Alamos National Laboratory, Los 

Alamos, NM [SRDB Ref. ID: 110072]

This reference concerns a response to the comment by L. Rosen, LANL, that it was his 

understanding that only one badge in three is read for MP Division and LAMPF visitor personnel 

whereas he thought it prudent to process all badges. The reference contains a description of 

many elements of the routine LANL personnel dosimetry program for LAMPF. It is stated that 

all beta/photon films issued to MP division and LAMPF visitors are processed, and read 

whereas all NTA neutron films are photographically processed but only one-third are read to 

determine neutron tracks. This occurs apparently because during this time period (JanuaryFebruary 1974) the average energy of measured neutrons is about 200 keV or less, and thus 

below the energy threshold for NTA film. To compensate for the unmeasured fluence of 

neutrons less-than the NTA energy threshold, LANL dosimetry applies a dose conversion factor 

of 0.024 rem per proton recoil track which is three times larger than the factor used for 5 MeV 
Rev 00, March 29, 2012 Page 35 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

neutrons. The memorandum does describe a method to allow processing and screening more 

NTA films which will be evaluated and also the effort underway to develop an albedo neutron 

TLD system to be implemented sometime during FY1976 depending on funding. 

Lawrence, J. N. P., Office Memorandum, dated March 22, 1974, entitled “Regular Versus Visitor 

Film Badges” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8176]

Apparently memo sent to LANL staff with a record of using visitor film badges. The memo 

states: “Visitor film badges are processed the same as regularly issued film badges. However, 

if the film from the visitor film badge indicates no significant exposure, no entry is made in the 

radiation exposure file of the person who wore the visitor film badge. The film and identification 

card for the visitor film badge is retained permanently but no radiation exposure record is 

generated for the person’s file. In the case of regularly issued film badges, the identification 

information for each person is already on file, and non-significant or zero exposures are entered 

in the person’s file.

The lower detection limit for the film badge is about 20 mrem for gamma exposures. If a person 

actually received 20 mrem, but 10 mrem was received by each of 2 visitor film badges, it is most 

probable that neither film badge would record a significant exposure. Had a single film badge 

been worn for this exposure (whether a visitor badge or a regularly issued film badge), the 20 

mrem exposure would be detected and would appear on that person’s radiation exposure 

record.

To secure a regularly issued film badge, please complete the attached form and return to me.

Littlejohn, G. J., Letter to Photodosimetry Evaluation Book, dated April 4, 1974, entitled “Kodak 

Type 2 Audit Program,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref 

ID: 8176]

In September 1973, an audit program was initiated by H-1 Personnel Dosimetry in accordance 

with a suggestion from AEC Albuquerque. The program monitors the accuracy of reported 

personnel exposures as derived from film badges. Audit films receive known dosages from 

60Co ranging from 0.10 R to 2.0 R. The films receive no preferential treatment and are 

processed along with the personnel and calibration films. The processing technician is not 

informed as to the exposures given the audit films. 

Audit procedures are as follows:

1. On or about the 15th of each month, 8 audit badges receive exposures ranging from 0.10 

R to 2.0 R: (60Co @ 40 cm – dose rate on 3/20/74, 67.64 mR/min)

2. Two audit films are selected at random and placed with each set of calibration films 

which will subsequently be developed with the personnel film.
Rev 00, March 29, 2012 Page 36 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

3. Positive densities are normally measured on the FD-11 densitometer. The Ansco is 

used when densities extend into the filter areas or when unusual filter patterns occur. 

Since the two densitometers differ in response, calibration films must be read on one or 

both densitometers when necessary. 

Littlejohn, G. J., Letter to Photodosimetry Evaluation Book, dated April 4, 1974, entitled “Change 

in the reading of DP West NTA Films,” Los Alamos National Laboratory, Los Alamos, 

NM, [SRDB Ref ID: 8176]

In April 1973, certain procedures were employed in the reading of fast neutron films issued to 

persons employed at D. P. West. In an attempt to increase the accuracy of the evaluated 

exposures, NTA films were read at least twice – each time by a different technician. The 

procedures followed are outline in greater detail in a memorandum dated 1/23/1974 entitled 

“Albedo-TLD versus Film Badge Study for Plutonium-239 Recovery Workers at D.P. West” by 

J.N.P. Lawrence.

The multiple reading technique was discontinued in January 1974. Demands placed on H-1 by 

LAMPF for increased fast neutron coverage, combined with a shortage of trained technicians, 

made it necessary to return to the 1 mm2scan by one technician. The evaluation factor of 24 

mrem/track about background (3 tracks) remains in effect.

Littlejohn, G. J., Letter to Photodosimetry Evaluation Book, dated June 4, 1974, entitled 

“Reading of NTA Film Issued to LAMPF Connected Personnel,” Los Alamos National 

Laboratory, Los Alamos, NM, [SRDB Ref ID: 8176]

Starting with the May 1974 film issue, all NTA films contained within the black and white cycolac 

badges are to be read in the following manner:

1. Scan four random fields in the F20 composite filter area. If no tracks are found, the 

reading is completed. Do not record a zero on the work sheet – leave blank. Enter 225 

as the remark code.

2. When one or more tracks are observed in any or all of the four random fields, proceed 

with a full 1 mmdscan. Enter fast rem dose (zeroes included) on a work sheet, using an 

evaluation factor of 0.024 rem/track. Do not use 225 as a remark code.

3. A full 1 mm2scan must be made on films which were worn with attached albedo neutron 

dosimeters.

4. To aid in the compiling of statistics on the four field method, certain information is to be 

maintained by each technician.

a. Total number of NTA films read

b. Number of films not requiring full 1 mm2scan.

c. Number of films requiring full 1 mm2scan.

d. The rem dose for each film which required a 1 mm2scan.
Rev 00, March 29, 2012 Page 37 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Reference is made to the above reading technique in a memorandum to J. E. Dummer 

“Personnel Neutron Dosimetry for LAMPF Personnel,” dated March 15, 1974, written by J.N.P. 

Lawrence.

Littlejohn, G. J., Letter to Photodosimetry Evaluation Book, dated June 4, 1974, entitled “New 

Practice in the Reading of NTA Films,,” Los Alamos National Laboratory, Los Alamos, 

NM, [SRDB Ref ID: 8176]

In the past, most NTA film track counting on a given film has been performed by a single 

technician. Experience has shown that variations can and do occur when the same film is 

counted by two or more technicians. To minimize track counting error and also to serve as a 

verification procedure (beginning with the August 1974 issue), all films which indicate a dose of 

200 mrem or more will be examined by a second technician. The average of the two readings 

will be fast neutron dose assigned to the badge wearer.

Engelke, M. J., Memorandum to G. Littlejohn, dated October 11, 1974, entitled “Neutron Film 

Badge Evaluation,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 

8176]

Average neutron energy measurements made on October 10, 1974 show a harder neutron 

energy than previously encountered at LAMPF. These measurements were made in the PDOR Trailer and immediate environs.

As a result of these measurements and the fact that the people listed herein spend 90% of their 

working time in the P-DOR area, their neutron film badge should be evaluated for 7.0 MeV 

neutron average energy.

Littlejohn, G. J., Letter to Photodosimetry Evaluation Book, dated October 24, 1974, entitled 

“Recording of NTA Film Counting Results,” Los Alamos National Laboratory, Los 

Alamos, NM, [SRDB Ref ID: 8176]

A computer program has been devised to directly convert the gross number of tracks counted in 

1 mm2 of film area to the fast neutron rem dose. Effective with the October 1974 issue period, 

the following information is to be entered on the NTA work sheets:

1. Gross number of tracks under page headings 44 to 47. (Do not subtract 3 track 

background)

2. When the film has been read by two or more persons, record initialed gross count under 

headings 44 to 47. Record the single averaged count under headings 48 to 51.

3. Between headings 56 to 59, record either an 8 or a 24. This determines whether 8 

mrem/track or 24 mrem/track is to be used in the evaluations.

4. Use remark codes when applicable as in the past.
Rev 00, March 29, 2012 Page 38 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

5. The new criteria for the reading of a film by a second person (replacing the old 200 

mrem or more) is 28 or more gross tracks when the track evaluation number is 8; 11 or 

more gross tracks when the evaluation number is 24.

Littlejohn, G. J., Letter to Photodosimetry Evaluation Book, dated October 24, 1974, entitled 

“NTA Film Rem/Track Conversion for LAMPF P-DOR Trailer Area Personnel,” Los 

Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8176]

In December 1973, an investigation of the fast neutron energies present outside of the biological 

shield at LAMPF indicated energies between 50-100 keV. See memorandum dated 12/15/1973 

to the Evaluation Book by J. N. P. Lawrence, “Rem/Track Neutron Conversion for LAMPF Film 

Badges.” As a result of this study, a dose of 24 mrem/track was applied as the evaluation 

factor.

During routine track-counting of films issued to P-DOR Trailer Area Personnel, it was noted that 

track lengths (about 4-5 MeV) appeared to be produced by energies higher than originally 

measured. This was confirmed in a survey by A. J. Miller, H-1, “Neutron Energy Levels at PDOR Trailer Area.” The confirmation of higher neutron energy levels made it necessary to 

correct, for certain individuals, reported neutron exposures for January through September 

1974. The correction was made by applying the 8 mrem/track factor, thereby reducing the 

earlier reported exposures by one-third.

The memorandum from M. J. Engelke (October 11, 1974) presents the names of persons 

whose records were changed. Since the workers occupying the trailer are primarily off-site 

users, the list may vary from one month to the next. A list of the appropriate users will be 

supplied by H-1 Personnel Dosimetry by the LAMPF Physics Section as changes occur.

Jalbert, R. A., Letter dated December 9, 1974 to J. N. P. Lawrence entitled “Neutron Dosimetry 

at HS-1,” Los Alamos National Laboratory, Los Alamos, NM {SRDB Ref ID: 22666, 

8176] 

Each film badge contains three films, two for beta-gamma and thermal neutron exposures, and 

one, an NTA film for registering proton recoils from fast neutrons. Tracks of protons with 

energies less than about 1 MeV are difficult or impossible to see by routine scanning. The 

neutron DE at these intermediate neutron energies must usually be inferred from the tracks 

registered at the higher energies. Thus the NTA film must be calibrated for the different neutron 

spectra that may be encountered. It has been found that two calibration factors cover pretty 

well the different fast neutron spectra at LASL likely to be involved in fast neutron exposures. 

The areas covered by these factors are DP West and the Los Alamos Meson Physics Facility 

(LAMPF) (except the P-DOR trailer area - Jim Simmons' group) on the one hand and the rest of 

the Laboratory (including the P-DOR trailer area) on the other.

Because of the higher component of intermediate and low energy neutrons at most areas of 

LAMPF and DP West, a higher DE per proton recoil track is assigned (24 mrem/track/mm2) at 
Rev 00, March 29, 2012 Page 39 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

these areas. A lower value (8 mrem/track/mm2) is assigned to the badges worn by personnel 

working in all other areas (including the P-DOR trailer area). Since reading each NTA film is a 

tedious process, normally only 1 mm2 of the film is read. In this film area background is 0 to 9 

tracks with 3 tracks being the average which is subtracted. Thus a negative net reading is 

possible although a zero DE is reported and recorded in such cases. For the same reason it is 

possible that a small reported fast neutron DE of up to approximately 50 mrem (140 mrem at DP 

West or LAMPF) may not be real. Of course higher DE's or repeated "insignificant" DE's are 

likely to be, at least partly, significant. Administratively-high or significant DE's may be followed 

up by an investigation resulting in a more accurate determination of the DE.

LAMPF film badges (black or white) contain the same films as the others (blue or gray). Each 

LAMPF NTA film is checked monthly since all LAMPF exposures may include a fast neutron 

component. Since most people who wear the blue/gray badges never see fast neutrons, the 

NTA film of these badges is only read for the small minority who may be exposed to fast 

neutrons. Many of those belonging to this group are determined from the form sent each month 

to the secretaries of those groups having people who are issued film badges (G. Dvorak 

receives the form for P-DOR.) All processed personnel films, whether read or not, are placed 

into permanent storage and are available for evaluation or re-evaluation if necessary. It is 

possible for a person's badge to be exposed to fast neutrons of an unusual spectrum or of 

different spectra involving, therefore, the possible requirement of· a still different calibration 

factor. The solution is to let H-l know each month on the same form used for determining which 

NTA films are to be read where the neutron exposures were obtained for that month. If a 

significant fast neutron exposure is registered and a calibration problem is involved, H-l will 

contact the individual in question. 

Much of the above information is contained in the booklet LA-3889 generally provided to LANL 

personnel containing information on the film badge or the Personnel Neutron Dosimetry Packet.

Hankins, DE, 1975, The Energy Response of TLD Badges Located on Personnel, Health 

Physics, Vol. 28, pp 80-81. 

Article describes studies of various filter combinations to achieve a tissue-equivalent energy 

response with LiF dosimeter as would be worn by personnel. 

1975

Los Alamos Dosimetry, “Photodosimetry Evaluation Book "Bible" Volume IIIb Procedures 1975-

77,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8192]

This reference contains many letters, memorandum and reports regarding Los Alamos 

personnel dosimetry system design, calibration, use, and dose assessment.
Rev 00, March 29, 2012 Page 40 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Vallario, E. J., D. E. Hankins, and C. M. Unruh, “Fifth AEC Workshop on Personnel Neutron 

Dosimetry, May 6-7, 1975,” BNWL-1934, Pacific Northwest Laboratory, Richland, WA 

[SRDB Ref ID: 18233]

The fifth AEC Personnel Dosimetry Workshop includes summary reports from several AEC Site 

contractors concerning their respective neutron dosimetry programs. A report by the National 

Bureau of Standards (NBS) is included describing the availability of new low energy 

monoenergetic neutron calibration facilities using funding provided by the AEC. Beams of 2 keV 

and 25 keV have been developed by the NBS. 

Blackstock, A. W., 1975, “LASL Automated Personnel TLD System to be Supplied by Harshaw 

Chemical Company,” Article in AEC 5th Personnel Neutron Dosimetry Workshop, Los 

Alamos National Laboratory, Los Alamos, NM, June, [SRDB Ref ID: 18233]

This article describes an automated LASL TLD system with a four chip dosimeter to be 

manufactured by Harshaw Chemical Company. The article describes several features of the 

planned automated system. 

H-1 Dosimetry & Records Section Letter dated July 29, 1975 to H-1 Health Physics Personnel, 

Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8192]

Evaluation Method (EVM) numbers are placed in the dose records to identify the algorithm used 

to calculate the dose. The EVM numbers used to evaluate the Kodak Type 2 Film contained 

within the cycolac badges are as follows:

 EVM 1: used to evaluate personnel exposures to plutonium or americium in significant 

quantities during chemical and metallurgical operations. During these operations, the 

material is usually contained in dryboxes, hoods or cells. Beta is not reported.

 EVM 4: used to evaluate thermal-neutrons, hard gamma and beta exposures.

 EVM 7: used to evaluate thermal-neutrons, x-rays and penetrating gamma exposures 

only.

Hankins, D. E., 1975, The Energy Response of TLD Badges Located on Personnel, Health 

Physics, Vol. 28, No. 1, pp 80-81.

Publication concerns measured photon energy response characteristics of TLD material in-air 

and positioned in the open window position of a TLD placed on a phantom..

1976
Rev 00, March 29, 2012 Page 41 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Lawrence, J. N. P., Letter to A. E. Dummer and A. M. Valentine, Memorandum dated October 

18, 1976, entitled “Personnel Neutron Dosimetry for LAMPF Personnel,” Los Alamos 

National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8192]

This reference describes ongoing evaluation neutron exposures of LAMPF personnel using NTA 

film and notes a March 15, 1974 memorandum in which LAMPF Management requested that all 

LAMPF workers be assigned film badges, and that all film badges be examined for neutron 

exposures. H-1 Personnel Dosimetry agreed to examine all LAMPF (black and white) film 

badges for neutrons on a trial basis. Presently (i.e. 10/18/1976) a large number of LAMPF film 

badges (~500) are issued each month. The time to read one square millimeter of the NTA fill 

requires extensive time for so many badges. Alternatively, it was decided to scan four 

microscope fields on each NTA film. If no proton recoil tracks were found, no neutron exposure 

would be recorded but a remark code would be attached to the record indicating that the film 

had been examined. If proton recoil tracks were found, the film would be read for the full one 

square millimeter area. For a total of 3 or less proton recoil tracks, zero exposure would be 

recorded (Cosmic ray background averages about 3 proton recoil tracks per square millimeter at 

LANL). Positive exposures would be recorded for film with more than 3 proton recoil tracks per 

square millimeter at the rate of 0.024 rem per track (in excess of 3). This procedure has been in 

effect since June 1974 for those months when LAMPF has been generating neutrons. 

The March 15, 1974 memorandum stated plans to determine if gamma exposure could be used 

as a neutron exposure indicator and the work underway to develop an albedo neutron TLD 

system which was expected to have greater sensitivity than NTA film for the leakage neutron 

spectra anticipated from LAMPF operations. No correlation has been established between 

measured gamma and neutron exposures. The new albedo TLD system is planned for 

implementation during late 1976 or early 1977.

The conclusion of this letter states: “It is apparent that the four-field-scan technique should be 

abandoned for LAMPF NTA films. A list of about 60 names has been received and starting with 

the September 1976 film badge issue a full one square millimeter area will be read. It is 

expected that the H-1 LAMPF Section will be kept informed of changes to this list.

Los Alamos Dosimetry, “Photodosimetry Evaluation Book "Bible" Volume V Procedures 1976-

1980,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8192]

This reference contains many letters, memorandum and reports regarding Los Alamos 

personnel dosimetry system design, calibration, use, and dose assessment.

1977

Hankins, D. E. 1977, Energy Dependence Measurements of Remmeters and Albedo Neutron 

Dosimeters at Neutron Energies of Thermal and Between 2 keV and 5.67 MeV, 

Lawrence Livermore National Laboratory, Livermore, CA, {SRDB Ref ID: 13994]
Rev 00, March 29, 2012 Page 42 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

This reference describes the use of improved NBS calibration facility capabilities that extend the 

measured response of remmeters and albedo neutron dosimeters about 1 decade lower in 

energy than has been possible previously. The NBS and cyclograph exposures were made with 

greatly differing experimental procedures. This is stated to give confidence in the accuracy of 

experimental procedures. 

1978

Los Alamos Dosimetry, “Photodosimetry Evaluation Book "Bible" Volume IVa Procedures 1978-

80,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8206]

This reference contains many letters, memorandum and reports regarding Los Alamos 

personnel dosimetry system design, calibration, use, and dose assessment.

Parrish, B, Memorandum to Health Physics Surveyors, dated July 17, 1978, entitled “BetaGamma and Neutron Surveys,” Los Alamos National Laboratory, Los Alamos, NM 

[SRDB Ref ID: 55566]

Beta-gamma and neutron surveys shall be taken daily of all gloveboxes which are contaminated 

or contain radioactive materials. Readings shall be posted and dated on glovebox stickers. 

Stickers are available in the H-l storage area if needed. A written report and room map shall be 

submitted to the H-l Office along with your personal log book each Friday. This will include the 

PF-4 Basement Vault. Readings shall be posted and updated on each individual vault entrance 

door. H-l Health Physics Surveyors assigned to the 100, 200, 300, 400 and Pu shipments are 

responsible for conducting the surveys.

LANL Staff novice, August 18, 1978, entitled “Film Badges to be Replaced,” Los Alamos 

National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8206]

The LANL Film badge is being replaced by a thermoluminescent dosimeter (TLD) badge. The 

TLD badge records personnel exposures from the same radiations measured by the current film 

badge. The TLD component is reusable and requires less time to process than film. The TLD 

badge has been used for visitors since May 1978. Certain LANL groups will be issued the TLD 

badges instead of film badges starting with the September 1978 badge issue. The complete 

conversion to these badges is expected to take several months.

Dummer, J. E., Group H-1 Health Physics, “Quarterly Progress Report, Group H-1 Health 

Physics July-September 1978,” Los Alamos National Laboratory, Los Alamos, NM 

[SRDB Ref ID: 13694]

On August 28, 1978 TLD badges were issued for the first time to regularly badged personnel. 

Only personnel issued badges by Maria Quintana received the TLD badges. These included the 

Fire department, Supply and Property, DOE, Pub, ISO, ENG, E, Q and H divisions. On 

September 26, 1978, personnel issued badges by Tish Peterson (WX, P, AT and J division) and 
Rev 00, March 29, 2012 Page 43 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Mary Garcia (MP, TA-55 OP, and CMB-5, 6, 11) will receive TLD badges. A handout, briefly 

describing the badge and how it should be worn, will accompany each badge. Due to the 

increased usage of TLD badges at LAMPF, 1000 black and white neutron badges are on order. 

TLD badges were calibrated to 252Cf in order to obtain correction factors to evaluate the 

exposures given by the University of Michigan in the Pilot Study on Dosimetry Performance. A 

summary of the Dosimetry Performance Pilot study stated that it appears that both the gamma 

and neutron exposure can be estimated within an accuracy of 15% when the badge is

exposed to a mixture of 252Cf and 60Co radiations.

Miller, A. J., Memorandum dated September 14, 1978 to E. Storm, entitled “Personnel Neutron 

Exposures,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref. ID: 110073]

This reference states that neutron energy measurements in the LAMPF experimental areas 

have shown that the average neutron energy is generally ~0.5 MeV in personnel occupied 

areas. Since NTA dosimetry film is insensitive to neutrons of energy <~0.7 MeV, the personnel 

dosimetry film has been calibrated to the track producing high energy neutron that are present 

in the neutron spectrum whose average energy is ~0.5 MeV. This calibration technique results 

in a “dose to track/mm2” conversion that is ~3 times that used for neutrons in the 1-14 MeV 

energy range, i.e., 24 mrem/track/mm2of film area, compared to 8 mrem/track/mm2 film area. 

The memorandum describes a review of assigned doses for two workers determined with the 24 

mrem/track/mm2dose conversion factor which were too high because of work in areas with 

predominantly higher neutron energies. Based on this memorandum, the doses to these two 

workers were modified to lower assigned doses. 

Blackstock, A. W., J. R. Cortez, G. J. Littlejohn, and E. Storm, 1978, Neutron Response of a 

New Albedo-Neutron Dosimeter, LA-UR-78-40, Los Alamos National Laboratory, Los 

Alamos, NM [SRDB Ref ID: 27246]

This reference describes the transition of the Los Alamos Scientific Laboratory (LASL) from a 

film badge to a badge containing thermoluminescent dosimeters (TLD's). This document 

describes the new LASL TLD badge, the response of the TLD badge to continuous spectra 

neutrons and to monoenergetic neutrons as a function of energy, a calibration method that does 

not require a detailed knowledge of the neutron energy spectrum, the accuracy to be expected 

from the dosimeter in neutron measurements and its limitations.

Field measurements were made to obtain 9- to 3-inch sphere ratios in two potential neutron 

exposure areas at LASL: a plutonium chemistry facility and the Los Alamos Meson Physics 

Facility (LAMPF). At LAMPF, the mean value of the ratio, measured in 18 different locations, 

was 0.17, with a standard deviation of 30%. At the plutonium facility, the average value of the 

ratio measured in 13 different locations was 0.57±35%. Assuming the relationship of the 
Rev 00, March 29, 2012 Page 44 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

measured ratio to the neutron energy is correct, these ratio values indicate an average neutron 

energy of <100 keV at LAMPF and of ~200 keV at the plutonium facility. This situation may 

explain why few neutron exposures have been observed at these facilities, since NTA film 

cannot detect neutrons with energies less than about 700 keV.

As described in this report, these measurements allow using measured calibration factors to 

increase the accuracy of neutron dose determinations providing (1) a person’s exposure can be 

determined to have occurred in one, or a very few, workplaces, and (2) that the ratio at each 

location does not change very much with time. The report describes the relative advantages and 

disadvantages of the NTA film dosimeter and the LASL albedo-neutron dosimeter utilizing 

TLDs. Although the sensitivity of the NTA film increases with increasing neutron energy, the 

film cannot measure exposures due to neutrons with energies less than about 700 keV. The 

TLD albedo-neutron badge response varies rapidly with incident neutron energy, decreasing 

with increasing energy. However, it can measure exposures from neutrons with energies < 700 

keV, since its response continues to increase down to the cadmium cutoff. The LASL albedoneutron badge is designed so that NTA film can be added to complement the TLD 

measurements for higher energy neutrons. The method was devised by Hankins (SRDB 8081) 

for calibrating the dosimeter in spite of the strong dependence of its response on neutron

energy. Our measurements thus far indicate that the method gives reasonably accurate 

exposure measurements in two LASL facilities where neutron exposures may occur.

Lawrence, J. N. P., Letter to Photodosimetry Evaluation Book, dated September 28, 1978,

entitled “Reportable TLD Exposures,” Los Alamos National Laboratory, Los Alamos, NM 

[SRDB Ref ID: 8206]

For reporting purposes, in compliance with the DOE Manual Chapters, non-zero exposures as 

recorded by the LASL TLD Badge, are defined to be total-rem exposures of 0.04 rem or more. 

In the B-1 Dosimetry records system, all measured values from 0.00 rem upwards will be 

recorded and attributed to the appropriate individual. This procedure is not appreciably different 

from that followed with the LASL film badge for the past 10 years, except that for film badge 

exposures less than 0.04 rem, no entry was made for the individual in the computerized record 

system. (The developed film was filed along with the completed visitor card, and the card-film 

pairing were sent to permanent record storage.) The TLD procedure is justified because of the 

statistical uncertainties in evaluating low exposures. The procedure is desired to reduce the 

excessive man-effort required to obtain mailing addresses, if reporting 0.00, 0.01, 0.02, and 

0.03 rem measurements were necessary.

The use of LASL TLD badges for visitors began in May 1978. The evaluated results for May 

and June were reported completely, demonstrating the enormity of the problem of

ascertaining mailing address. The new reporting procedure becomes effective for the

July 1978 visitor TLD issue. For regularly issued TLD badges (starting with the September 1978 

issue), exposures will be reported as measured, until such time that a

statistical study is completed which defines the minimum detectable level for the system.
Rev 00, March 29, 2012 Page 45 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Lawrence, J. N. P., Letter to File, dated October 6, 1978, entitled “Los Alamos Criticality 

Accidents 1945-19461 Personnel Exposures,” Los Alamos National Laboratory, Los 

Alamos, NM, [SRDB Ref ID: 8206]

The purpose of this memo is to document the exposures to be entered in the H-l Dosimetry 

Computer Record for persons involved in the three criticality accidents occurring at Los Alamos 

in 1945-1946. None of the personnel involved wore film badges or other personnel dosimetry 

detectors. Calculations of the personnel exposures exist in several source documents (referred 

to herein), but a simple reference to this material is inadequate because of differences in the 

calculated results. This memo will designate the exposures to be entered in the computer 

record, identify the source documents, point out the differences in the exposure estimates, and 

provide an explanation of why the particular exposure estimates were chosen.

Vallario, E. J., D. E. Hankins, J. Harvey and P. E. Bramson, “Seventh DOE Workshop on 

Personnel Neutron Dosimetry, October 23-24, 1978,” PNL-2807, Pacific Northwest 

Laboratory, Richland, WA [SRDB Ref ID: 26723]

This workshop was the seventh of a series and was held on October 23-24, 1978, at the Central 

Electricity Generating Board, HQ, London, England. This Workshop was held in London to 

permit greater involvement of the European experts than has been experienced at past 

workshops. It was hoped that work being performed in Europe might be leading to new 

dosimetry techniques for application within the DOE contractor organization. Generally, no new 

ideas, concepts or breakthroughs were identified during two days of informal discussions. The 

detection of intermediate energy-neutrons continues to be an unsolved problem.

1979

Cortez, J., Letter to Photodosimetry Evaluation Book, dated May 10, 1979, entitled “TA-55 

Vault Area Doubled Badge Experiment,” Los Alamos National Laboratory, Los Alamos, 

NM [SRDB Ref ID: 8206]

On February 26, 1979, two non-cadmium TLD badges were requested for two employees 

working in the vault area of TA-55. These badges were issued and were worn along with their 

respective, regularly issued, TLD cadmium badges during the month of March, 1979. Badges 

for both employees were read and evaluated on April 3, 1979. The following table has the 

results.

Employee Badge Type Calculated dose, mrem

Nonpenetrating Penetrating Neutron

Employee #1 Non-cadmium Badge 82 85 194

Cadmium Badge 63 62 171

Employee #2 Non-cadmium Badge 119 117 230

Cadmium Badge 121 117 210
Rev 00, March 29, 2012 Page 46 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Health Safety and Environment Technical Manual, Technical Bulletin, “Thermoluminescent 

Dosimeter Badge,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref ID: 

8206]

This bulletin describes the components, operation, and limitations of the thermoluminescent 

dosimeter (TLD) badges used at LASL for personnel radiation exposure monitoring. It also 

describes the procedures for reading the badges, recording dose information, and distributing 

dose reports. A number of recommendations are included for those who wear TLD badges.

Lawrence, J.N.P., Letter to Distribution, dated October 26, 1979, entitled “Discontinue Use of 

Pancake Probe Instruments For Alpha Monitoring Until Further Notice,” Los Alamos 

National Laboratory, Los Alamos, NM [SRDB Ref ID: 55566] 

Effective immediately, the use of pancake probes on G-M instruments for alpha monitoring shall 

be discontinued, except as noted below. A preliminary investigation has indicated that the 

pancake probe is incapable of detecting less than about 1000 dpm of Pu alpha. This preliminary 

investigation has shown that the net cpm (gross cpm - bkg cpm) must be multiplied by a factor 

from 10 to 20 to convert to "dpm" for Pu alpha. No officially accepted value has been 

established for converting readings on Ludlum Model 14's with a mR/hr meter reading. Until 

further notice, use only alpha monitoring instruments (PeeWee's, PAC-7, PAC-1SAGA, Ludlum 

139, Ludlum 11, Ludlum 12) for all alpha monitoring.

Littlejohn, G. J., Letter to Photodosimetry Evaluation Book, dated October 30, 1979, entitled 

“The Use of “Visitor” Dosimeter Badges at the Los Alamos Scientific Laboratory,” Los 

Alamos National Laboratory, Los Alamos, NM [SRDB Ref ID: 8206]

This is an historical analysis of visitor badge use. At LASL, a "visitor" badge is a badge 

temporarily issued to an individual who does not have a "permanent" or regularly assigned 

badge.

Film badges, used as a means to measure personnel exposures to radiation, were first issued 

by the Health Group on 2/19/45. Prior to and after the Trinity Test on 7/16/45, it is not possible 

to classify a particular badge as being either a visitor badge or a permanent badge. At that time, 

badges .were given to various operating personnel for distribution and no attempt was made to 

record the person's employment status or parent organization. The first record of a visitor badge 

appears in LA Notebook 11304, where a badge was worn at Pajarito Site on 12/9/46. After that 

date, almost all of the Notebooks have separate entries for visitor, permanent, and planted 

badges. Information as to the wearer's name, film badge number, and dates worn, were 

recorded on "Visitor Register Forms", then given to the Health Group for entry in the LA 

Notebooks. After film processing and dosage evaluation, exposure reports were prepared in 

inter-office memorandum form. Reports were distributed to the leader of the Health Group, 

involved supervisory personnel, and the Hematology Lab.
Rev 00, March 29, 2012 Page 47 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

This document is much longer with examples of various records.

1980

Storm, E., Letter to Photodosimetry Evaluation Book, dated January 6, 1980, entitled “Error in 

Dose Evaluations (Neutron Evaluation Program),” Los Alamos National Laboratory, Los 

Alamos, NM [SRDB Ref ID: 8206]

In March 1979, an error was found in the computer program which resulted in the incorrect 

neutron evaluations of certain TLD badges. The badges affected were Types 5 (light yellow), 

and 6 (light blue), which were worn during the months of September 1978 through February 

1979. For these months, neutron exposures were reported low by

a factor of 6, since a correction factor of 0.5 had been used instead of a factor of 3.0.

Except for the Form 630 exposure reports, which had already been circulated, corrections were 

made to all other dosimeter 1istings and computer entries. The computer program was also 

corrected.

Anonymous, LANL Record dated January 23, 1980, entitled “Employee Health Physics 

Checklist,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref. ID: 110058]

This reference contains numerous LANL forms of routine monitoring activities. One of the forms 

(HS&E 5-1A) is titled “Employee Health Physics Checklist” and involves a review of potential 

workplace exposure scenarios. The external section includes checklists as follows:

 Pu x-rays

 Machine x-rays

 Neutrons, less than 2 MeV

 Neutrons, over 2 MeV

This information is apparently used to determine which types of dosimeters to be assigned such 

as a Personal Neutron Dosimeter (PND) and finger rings.

Gutierrez, J., Memorandum dated February 6, 1980 to R. R. Showalter, entitled “TLD Survey, 

SM-316,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref. ID: 109556]

This reference appears to be a routine report of TLD measurements at selected locations. 

Three of the 34 TLD packets showed positive results described as follows:

a) Target room, in line with the beam: total dose = 1.12 rem, average dose per shot = 25 

mrem

b) In the Maze: total dose = 0.02 rem, average dose per shot = 0.4 mrem.

c) Perimeter fence, adjacent to SW corner of SM-316: total dose = 0.01 rem, average dose 

per shot = 002 mrem.
Rev 00, March 29, 2012 Page 48 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

There are 42 TLDs strategically placed within and throughout (sic without) SM-316. Special 

dosimeters (10 each) are in place around the facility for neutron dosimetry. For the December 

1979 dosimetry records, no personnel in the group in question showed a positive recorded 

neutron dose.

Buchanan, R., Memorandum dated February 10, 1980 to File, entitled “Average neutron Energy 

and Dose Rate Measurements in Counting Houses in Area A,” Los Alamos National 

Laboratory, Los Alamos, NM [SRDB Ref. ID: 109559]

This reference concerns results of a special radiation survey performed on February 12, 1980 of 

the counting houses in Area A to determine the average neutron energy. A moderated BF3 and 

a proton recoil counter were used. The beam parameters were: 800 MeV, 560 μA at A-1, 120 

PPS, and 550 μsec. The results are:

Location Flux,

(n/cm2-sec) ± 2σ Average E, (KeV/n) ± 2σ

Dose Rate 

Neutron 

(mrem/h)

Gamma 

(mR/h)

Trlr. 433 0.32 2.7% 1030 13% 0.04 0.05

LEP ct. h. 7.33 1.7% 894 8.8% 0.81 0.22

SMC ct. h. 9.50 1.9% 342 16% 0.53 0.19

P

3

ct. h. 3.17 3.3% 482 24% 0.23 0.10

EPICS ct. h. 6.89 2.3% 453 17% 0.46 0.16

Area A floor* 7.44 2.2% 191 24% 0.25 0.5

* by Remote Handling Trlr.

Dosimetry and Records Section, Office Memorandum, dated March 21, 1980, entitled “New 

Personnel Monitoring (Body) Totals Form,” Los Alamos National Laboratory, Los 

Alamos, NM [SRDB Ref ID: 8206]

The reporting form for personnel monitoring results has been redesigned 1) to conform to the 

current trend in dosimetry measurements of describing exposures in terms of penetrating and 

non-penetrating doses and 2) to more accurately express the measurements made with the new 

TLD badge system.

Except for the removal of birth year, the identification information on the old and new forms has 

been retained. Missing from the new forms are the columns entitled:

beta-rad, gamma-r, gamma-rem, thermal neutron-rem and fast neutron-rem. 

The new form heading "Non-penetrating Rad" is intended to indicate the total skin dose from 

external ionizing radiation. It is equivalent to the old beta-rad plus gamma-.rem, or the old 

gamma-r doses. The new form heading "Penetrating-rem" is intended to indicate the total whole 

body dose from external ionizing radiation. It is equivalent to the old gamma-rem dose.
Rev 00, March 29, 2012 Page 49 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

The new form contains only a single "neutron-rem" heading. The exposures indicated

in this column are primarily the albedo (body scattered) neutron dose as measured by

the TLD badge. However, for those few cases where a "piggy-back" NTA film is part of

the badge, the fast neutron dose recorded by the NTA film is added to the albedo

neutron dose, and an entry "NTA" is included under the REMARKS column. 

The exposures recorded under the heading "Tritium-rem" is the whole body dose due to

tritium in the body. It is calculated from the tritium urine assay results. Under the heading "Totalrem" is tabulated the sum of the "penetrating-rem," "neutron-rem," and "tritium-rem," similar to 

the procedure used on the old forms. 

Under "REMARKS," in addition to the "NTA" indication, are three other possible entries: "LATE" 

to indicate TLD badge results from badges issued prior to the month being reported; "NTS" to 

indicate exposures reported by the Nevada Test Site; and "AWAY" to indicate exposures 

reported from other installations visited by LASL staff. Also indicated is the latest date for which 

"NTS" and "AWAY" exposures apply. 

The new forms are preprinted with the' Privacy Act marking "PERSONAL INFORMATION." 

PERSONAL INFORMATION designates information of a privileged nature, relating to the 

Federal Privacy Act of 1974. 

Littlejohn, G. J., Letter to Dosimetry Personnel and Evaluation Book, dated June 6, 1980, 

entitled “TLD Audit Program,” Los Alamos National Laboratory, Los Alamos, NM [SRDB 

Ref ID: 8206]

The audit program monitors the accuracy of reported personnel exposures as measured by the 

TLD dosimeter badges. This program is similar to the one used with film badges during the 

years 1973 through 1979.

Audit Procedures

Each month 12 badges are taken, at random, from the supply of temporary badges prepared for 

use in the field - these serve as audit badges. Ten of the badges are exposed to a 60Co source 

and receive exposures ranging from 10 mR to 1000 mR. Changes are made in the delivered 

exposures each month. The remaining 2 badges receive no exposure. Following exposure, the 

badges and identification cards are returned to the appropriate technician for processing. Audit 

badges are included with the personnel badges, and after processing the reported exposures 

are compared to the delivered exposures.

Blackstock, A. W., Letter to J. N. P. Lawrence dated November 25, 1980, entitled “TLD Badge 

Neutron Correction Factors at LAMPF,” Los Alamos National Laboratory, Los Alamos, 

NM, [SRDB Ref ID: 8206]
Rev 00, March 29, 2012 Page 50 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

The TLD albedo badge neutron response varies by three orders of magnitude over the energy 

range 50 keV to 14 MeV. Therefore, appropriate correction factors must be determined for each 

area where personnel neutron exposures can occur. Such factors have been measured in a 

number of locations at LAMPF and the results are summarized below for the noncadmium 

badge on a polyethylene slab.

Area

Neutron Correction 

Factor

(N rem/60Co R)

WNR Experimental Room #1 0.27

Catwalk, near EPICS Pumphouse 0.082

Mezzanine, Top of South Stairs 0.087

LEP Counting House 0.13

South catwalk near Beam-on Light 0.16

Test Channel 0.15

Test Channel Instr. Rack Area 0.29

A. J. Miller stated that the WNR area is the only area at LAMPF where the personnel assigned 

work exclusively in that area. None of the other personnel work only in one area. Also, relatively 

few people work in the Test Channel Instrument Rack area at any time, and the crews change 

with changing experiments during an operating cycle.

We have been using a neutron correction factor of 1.0 for all TLD badges worn at LAMPF, 

which are the cadmium type. It is now recommended that the noncadmium badge be worn at 

LAMPF and that a neutron correction factor of 0.20 be used for all areas at LAMPF.

Lawrence, J. N. P., Letter to R. Stafford, dated December 1, 1980, entitled “Evaluation of TA-55 

Neutron Exposures,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 

8206]

This reference concerns minutes of a Personnel Dosimetry staff meeting to discuss the 

Blackstock letter of 11/25/1980 containing measurements of the required neutron correction 

factors at TA-55. This data was examined, along with the September 1980 and the January 

through September 1980 exposure information for TA-55 workers. Conclusions of the meeting 

included:

1. To improve the accuracy of neutron exposures recorded for TA-55 workers, it was decided 

to use 3 pairs of TLD badges at TA-55, with 3 different neutron correction factors. Three 

different operational activities at TA-55 were defined:

a. Glove box workers using boxes with hydrogenous' shielding who spend 60% or more 

time working-,n-these glove boxes. Neutron correction factor 0.1. Light brown and dark 

brown badges to be issued.
Rev 00, March 29, 2012 Page 51 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

b. Glove box workers using boxes without hydrogenous shielding who spend 60% or more 

time working in these glove boxes. (Possible inclusion of persons working with PuBe 

sources in boxes with hydrogenous shielding; data being developed this week.) Neutron

correction factor 1.0. Light purple and dark purple badges to be issued.

c. All other TA-55 workers, including persons working in the general PF-4 area, 

supervisors, HP surveyors, vault workers, process coordinators, CMB-11 count room 

workers, and persons who divide their time approximately equally between glove boxes 

with and without hydrogenous shielding. Neutron correction factor 0.5 (this is the same 

as has been used throughout 1980 at TA-55 for all workers). Yellow and aqua badges to 

be issued.

2. For this system to work, the H-1 TA-55 Section must supply the Dosimetry Section with the 

names and Z-numbers of the persons in each of the 3 categories by the 15th of the month 

preceding the TLD badge issue. This time frame is necessary for the Dosimetry Section to 

prepare the next month's TLD badges in the proper color (and with the proper coding). I 

suggest that after the procedure is established, the changes from the previous month be 

identified by “*”s.

3. In addition, the H-1 TA-55 Section must supply the Dosimetry Section with any corrections 

to the original color (and coding) when the TLD badges are returned for processing. 

Hopefully, these changes will not exceed 10 per month or the system will not be functionally 

operative from the Dosimetry Section's point of view (due to the necessity of correcting the 

computer data bank). 

4. The Dosimetry Section will be ordering the new badges this week. Depending on the 

delivery time and the time to add the filters and labels to the badges, the system cannot be 

instituted before February 1981, or more probably March 1981. I suggest that the H-1 TA55 Section initiate and operate their notification phase of the operation as soon as possible 

in order to discover and correct their difficulties before the system becomes effective.

Lawrence, J. N. P., Letter to E. Storm, dated December 3, 1980, entitled “TLD Badge Neutron 

Correction Factors at LAMPF,” Los Alamos National Laboratory, Los Alamos, NM, 

[SRDB Ref ID: 8206]

I concur with A. W. Blackstock's recommendation that noncadmium TLD badges be issued at 

LAMPF, using a neutron correction factor of 0.2 for all LAMPF areas (see 12/1/80 Letter above). 

From our discussions, I understand that H-1 will prepare light green and dark green badges for 

LAMPF, starting by the February 1981 issue (since LAMPF does not anticipate any neutron 

exposure in January 1981). Using the noncadmium badge with the 0.2 neutron correction factor 

is approximately equivalent to using the cadmium badge with a correction factor of 1.0 and 

should not result in any significant change for large exposures (>100 mrem). However, the 

noncadmium badge will give a factor of 5 increase in sensitivity, enhancing the reliability of low 

exposures
Rev 00, March 29, 2012 Page 52 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

1981

Storm, E., P. L. Buslee, A. W. Blackstock, G. J. Littlejohn, J. R. Cortez, R. V. Fultyn and J. N. P. 

Lawrence, 1981, The Los Alamos Thermoluminescence Dosemeter Badge, Rad Prot 

Dosi, Vol. 1, No. 3 p 209-219, [SRDB Ref ID: 27290] 

The Los Alamos thermoluminescence dosimeter (TL.D) provides an accurate and versatile 

instrument for the measurement of ionizing radiation and is capable of passing the Health 

Physics Society Standard, -Criteria for Testing Personnel Dosimetry Performance" For photons 

above 100 keV in energy, the badge can measure dose without the need of correction factors. 

However, below 100 keV correction factors are necessary but the badge can be used as a 

crude spectrometer to estimate the photon energy and thus the appropriate correction factors. 

For a mixture of low and high energy photons, an average energy is obtained that varies with 

the mixture. Low energy photons can be distinguished from beta rays. For a mixture of 90Sr 

beta and 6OCo gamma radiation, the fraction of each component can be determined and 

appropriate correction factors applied. To evaluate neutron doses, the badge reading must be 

supplemented with a knowledge of the source and moderating material, or on-site determination 

of correction factors.

Umbarger, J. Letter to J. N. P. Lawrence, dated June 4, 1981 entitled “Use of NTA Film for 

Personnel Neutron Dose Measurements at Los Alamos,” Los Alamos National 

Laboratory, Los Alamos, NM, [SRDB Ref ID: 8209]

Until recently, the TLD cadmium badge has been issued to personnel at LAMPF. The response 

of the cadmium badge to neutrons, over a range of 0.05 to 14 MeV, decreases with increasing 

energy by three orders of magnitude and is relatively insensitive to fast neutrons. For example, 

assuming 10 mrem is the minimum detectable dose when the neutron correction factor equals 

unity, the minimum detectable doses at 1, 5 and 14 MeV are 100, 400 and 500 mrem, 

respectively. Because early measurements at LAMPF indicated the presence of fast neutrons 

in certain areas, the TLD badge is supplemented by the Kodak NTA film, which is placed in a 

Cycolac “piggy-back” holder attached to the TLD badge. The NTA film records proton recoil 

tracks over a range of approximately 0.7 to 14 MeV; below 0.7 MeV the tracks are too short to 

be distinguished. Three tracks are considered background and a dose of 24 mrem is assigned 

to each track above background. To obtain the total neutron dose, the TLD and NTA film doses 

are summed.

The number of gross tracks recorded each month on the NTA film during the period of June 

1979 through March 1981 is shown below:

DISTRIBUTION OF GROSS TRACKS ON PERSONNEL NTA FILM

Gross 

Tracks

1979 1980

Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr
Rev 00, March 29, 2012 Page 53 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

0 65 63 59 54 24 17 14 36 42 23 28

1 12 11 11 16 15 12 10 7 0 12 11

2 2 3 3 6 5 6 10 0 0 6 3

3 0 0 1 2 0 5 2 0 0 3 1

**** Greater than background counts below 

4 0 0 0 0 0 0 1 0 0 1 0

5 0 0 0 0 0 1 0 0 0 0 0

10 0 0 0 0 0 0 1 0 0 0 0

Gross 

Tracks

1980 1981

May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar

0 33 31 31 34 22 31 27 (a) (a) 16 17

1 9 9 8 4 9 8 10 9 13

2 2 1 3 3 7 2 23 7 6

3 0 1 1 0 1 0 0 1 1

** ** Greater than background counts below****

4 0 0 0 0 0 0 0 0 0

5 0 0 0 0 0 0 0 0 0

10 0 0 0 0 0 0 0 0 0

a. No film issued. LAMPF shut down.

For the 964 films issued during this period, only 4 gave a positive reading. The positive NTA 

film readings, along with the net number of tracks, film dose, and corresponding TLD dose, are 

summarized in the following:

POSITIVE NTA FILM READINGS

Month Net 

tracks

NTA (rem) TLD (rem)

Nov 79 2 0.05 0.00

Dec 79 1 0.02 0.00

Dec 79 7 0.17 0.53

Mar 80 1 0.02 0.36

Of the 4 positive readings, 3 recorded only 1 or 2 tracks above background. Although the film 

recording 7 net tracks appears to have received a valid fast neutron exposure, the TLD dose 

exceeds the film dose by a factor of 3, indicating lower energy neutrons predominate.

Of the 964 TLD badges containing film, 205 gave positive TLD readings, indicating the presence 

of low energy neutrons. The doses tend to be low, only 5 exceeding or equal to 0.1 rem as 

shown, along with the corresponding NTA film dose, in the following:
Rev 00, March 29, 2012 Page 54 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

TLD DOSES ≥ 0.1 rem

Month TLD (rem) NTA (rem)

Jun 79 0.13 0.00

Dec 79 0.53 0.17

Mar 80 0.36 0.02

Mar 81 0.10 0

Mar 81 0.17 0

The NTA film readings indicate negligible dose even for the larger TLD doses with only one 

exception (Dec 79).

Lawrence, J. N. P., Letter to J. Umbarger, dated June 11, 1981, entitled “Discontinuation of NTA 

Film for Personnel Dosimetry,” Los Alamos National Laboratory, Los Alamos, NM, 

[SRDB Ref ID: 8209]

This reference expresses agreement with the previous letter from J. Umbarger (dated June 4, 

1981). It does state that the regular issue of NTA film for LAMPF personnel should be 

discontinued as of the July 1981 dosimeter issue. It also suggests another possibility which is 

to assign NTA film to only a few selected workers based on trend in TLD measured doses rather 

than simply assigning 40 combination TLD/NTA film dosimeters each month. 

Gutierrez, J., Memorandum dated July 9, 1981 to J. Gallimore, entitled “Radiation Survey 

Results,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref. ID: 109553]

This reference appears to be a report of special Li-6 TLD measurements at selected personnel 

desk locations. The Li-6 chips were used in a H2O moderator with the expressed purpose of 

the survey to monitor for neutrons which could possibly be generated from the east bay of SM40, AT-1’s, 20 MeV Linac Injector Gun. Maximum beam parameters during the period were 

specified in the report. Survey results for 4 personnel desk locations were presented ranging 

from 3.5 to 5 mrem during the 34 day period from June 4 through July 8, 1981. 

Lawrence, J. N. P., 1981, “Dosimetry Records and Radiation Hazards Questionnaire,” Los 

Alamos National Laboratory, Los Alamos, NM, September 19, [SRDB Ref ID: 8209]

The LANL input to this questionnaire identifies several reference documents as follows:

LAM-620 Los Alamos Health Group Film Badge Techniques, C. Buckland, 1974

LA-1107 A Method for Monitoring X-rays Using Eastman Type K Film, E. Storm & E. 

Bemis, 1950

LA-1220 The Response of Film to X-Radiation of Energy Up to 10 MeV, E. Storm, 

1951

LA-1284 The Response of Sensitive 552 DuPont Film to Beta Radiation, E. Storm, 
Rev 00, March 29, 2012 Page 55 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

1951.

LA-1923 A Film-Badge Method of Differential Measurement of Combined ThermalNeutron and Gamma-Radiation Exposures, F. Kalil, 1955

LA-2494 Photodosimetry Procedures at Los Alamos, G. J. Littlejohn, 1960

LA-3001 The Development of Film Badges Containing Multi-element Filters to 

Reduce the X-Ray Energy Dependence of Photographic Film, E. Storm & S. 

Shlaer, 1961.

LAUR81-1799The Los Alamos Thermoluminescent Dosimeter Badge, E. Storm, etc., to be 

published in 1982 in Radiation Protection Dosimetry.

1982

Littlejohn, G. J., Letter dated March 4, 1982, entitled “Change in Neutron Correction Factor for 

OWR Personnel,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 

8209]

A review of the neutron correction factor being used at the Omega West Reactor for CNC-5 

personnel TLD badges was completed on 2/19/82. Neutron measurements were made with a 

9” diameter polyethylene sphere, RM-16 rate meter, and an Ortec scaler. TLD badges, 

mounted on a 1.5” polyethylene slab, were exposed beside the sphere. Two exposures runs 

were made: 1) The first from 2/1/82 to 2/10/82, and the 2) from 2/11/82 to 2/19/82. The 

detectors, badges, and sphere were placed near the north face of the reactor. This is an area 

where significant personnel exposures are most likely to occur. The results are:

Detector Run #1 Run #2

Neutron, mrem Ratio Neutron, mrem Ratio

9” Sphere 73.1 10.7 44.4 12.7 TLD Badge 761 564

The results indicate that a correction factor of 0.1 should be applied to the neutron dose instead 

of the 0.5 in current use. It is recommended that this change be made in the evaluation 

procedures.

1983

Littlejohn, G. J., Memorandum dated April 25, 1983 entitled “Dosimeter Badges,” Los Alamos 

National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8209]

This memorandum requests that the following message be placed in the NewBulletin.

DOSIMETER BADGES

Wear your dosimeter badge visibly exposed on the front of your person between the waist and 

the neck. It should be worn at all times when working or visiting in the Laboratory areas where 

badges are required. Since the purpose of the badge is to measure your occupational 
Rev 00, March 29, 2012 Page 56 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

exposures, the badge should not be worn when receiving dental x-rays or medical treatments 

involving the use of radiation.

Mundis, R., and Larkin, J. E., Memorandum dated April 26, 1983 to A. J. Miller, entitled “WNR 

Facility SOP,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref ID: 55688]

This memorandum concerns editorial changes to the Weapons Neutron Research (WNR) 

facility Standard Operating Procedure (SOP). This document describes facility-specific survey, 

control and response activities. For example, a survey is required to verify that all areas where 

the radiation level is greater than 10 mrem/h and all beam paths are identified with a proper 

barrier." Also, for personnel entry into an area with a >10 mR/h field, pocket dosimeters are 

required. Another section concerns notification of the WNR RSO and the LAMPF H-1 office of 

all shipments of sources and radioactive materials (such as research sources and experimental 

apparatus) to WNR.

Mundis, R., Memorandum dated September 12, 1983 to R. Ryder, entitled “Neutron 

Measurements in Line D and ER-1, August 30, 1983,” Los Alamos National Laboratory, 

Los Alamos, NM [SRDB Ref ID: 55686]

Reference describes results of measurements of neutron intensity in Experimental Room 1 (ER1) while the beam was striking a tungsten beam block with a known beam intensity. Moderated 

indium foils that have a fairly uniform response to neutrons in the energy range from 0.02 to 20 

MeV were used as the primary measuring device. These measurements showed that 

substantial neutron doses could occur in ER-1 if beam shutdown capabilities do not work as 

designed. 

Larkin, J. E., LAMPF HSE-1, Memorandum dated November 4, 1983 to A. J. Miller, entitled 

“October Area A Balcony TLD Dosimetry Plants,” Los Alamos National Laboratory, Los 

Alamos, NM [SRDB Ref ID: 55689]

This memorandum concerns results of TLD measured photon and neutron radiation exposure 

levels detected on the Area A balcony during October. 

A. Badge 2136-on monitor stand gamma - 1.36 mR/h, beta - 0.26 mR/h, neutron - 1.2 

mrem/h, Total penetrating radiation - 2.56 mrem/h

B. Badge 2137 - on work table, gamma - 0.94 ~R/h, beta - 0.15 mR/h, neutron - 1.02 

mrem/h, Total penetrating radiation - 1.96 mrem/h

1984

Mundis, R and J. Miller, Memorandum dated January 10, 1984 to R. Woods, entitled “WNR Blue 

Room High Current Run Radiation Surveys,” Los Alamos National Laboratory, Los 

Alamos, NM [SRDB Ref. ID: 109441]
Rev 00, March 29, 2012 Page 57 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Reference contains results of radiation surveys on and around the shielding berm over the Blue 

Room conducted on December 22, 1983 by members of the LAMPF Health Physics staff. 

Gamma and neutron dose rates were measured at several locations. The data also showed 

that significant neutron activation of the walls and structure of the Blue Room may occur at high 

beam currents.

McAtee J. L., Memorandum to R. Stafford, dated February 6, 1984, entitled “TA-55 Neutron 

Dosimetry Factor Re-Evaluation,” “Photodosimetry Evaluation Book "Bible" Volume VI 

Procedures 1980-1989,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref 

ID: 27288, 8209]

This reference contains the final report for the neutron dosimetry factor re-evaluation at TA-55. 

Correction factor measurements were made at numerous locations throughout PF-4 by 

comparing the time-integrated response of a 9 inch spherical neutron rem meter to the response 

of TLD badges mounted upon the face of a 40 x 40 x 15 centimeter Lucite phantom slab. The 

correction factor is the ratio of the rem meter reading to the response of the TLD badge. A 

summary of the measured neutron correction factors follows:

Work Area Average Correction Factor

100 Area 0.79

206/207 0.29

208 0.72

209 0.85

319 0.65

327 0.52

401 0.75

409 0.71

420 0.76

429 0.56

Vault 0.63

Miller, A. J., Memorandum dated April 9, 1984 to D. G. Vasilik, entitled “TLD Badge Neutron 

Correction Factor at LAMPF,” Los Alamos National Laboratory, Los Alamos, NM [SRDB 

Ref. ID: 109565]

This reference concerns a meeting among health physics and operational staff regarding the 

appropriate correction factor to be used for LAMPF neutron personnel dosimetry evaluations. 

Based upon considerations of measured neutron spectral and dose equivalent data, it was 

agreed that the LANL noncadmium badge should remain in use at the LAMPF, and that a 0.2 

neutron correction factor continue to be used. A table of neutron rem measurement 
Rev 00, March 29, 2012 Page 58 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

comparisons is provided between TLD and 9” rem-meter measurements showing minimum and 

maximum correction factors of 0.02 and 0.4, respectively.

Hankins, D. E., 1984, Beta- and Gamma-Dose Measurements of the Godiva IV Critical 

Assembly, Health Physics Journal, Vol. 46, No. 3, pp 561-579, [SRDB Ref ID: 35110] 

The beta and gamma dose rates from the los Alamos national Laboratory Godiva IV Critical 

Assembly were measured at numerous distances from the assembly four and twelve days 

following a burst. Information was obtained on the beta-particle spectra using absorption curve 

studies. The beta/gamma dose-rate ratio as a function of distance from the assembly was 

determined. Shielding provided by various metals, gloves and clothing was measured. The 

beta- and gamma-ray doses measured were compared with a film packet used in the past at the 

Nevada Test Site with two types of current TLD personnel badges. Measurements made with a 

commercial thin-window ion chamber instrument are compared with the dose rates obtained 

using other dosimeters.

LANL Bulletin, 1984, “Los Alamos Thermoluminescent Dosimeter Badge,” Los Alamos National 

Laboratory, Los Alamos, NM, December, [SRDB Ref ID: 8209]

This bulletin describes the components, operation, and limitations of the thermoluminescent 

dosimeter (TLD) Los Alamos badges used for personnel radiation exposure monitoring. It also 

describes the procedures for reading the badges, recording dose information, and distributing 

dose reports. A number of recommendations are included for those who wear TLD badges.

Lawrence, J. N. P. Letter to T. F. Gesell, DOELAP Testing Administrator date December 14, 

1984 concerning “Completed Questionnaire to Participate in DOELAP Pilot Performance 

Testing,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8209]

The completed DOELAP Pilot testing program application requires information regarding the 

categories selected for testing. The LANL application states that accreditation is not sought for 

Category VB (Beta, uranium), nor for the low energy component of Category VA (Beta). It is 

stated that while LANL testing indicates that routine evaluation procedures would evaluate beta 

doses from contact with uranium adequately, the calibration method is not consistent with the 

geometry under which most beta doses are received. No person is believed to be currently 

working with and receiving beta exposures from 204Tl. If (and when) such work is undertaken, it 

will be necessary to modify our standard evaluation procedures for the identified TLD badges 

used for that work because LANL standard evaluation procedure can not identify 204Tl betas. . 

1985

McAtee, L, Memorandum to B. McKerley, dated April 16, 1985, entitled “Dose Rate 

Measurements,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref ID: 

54539]
Rev 00, March 29, 2012 Page 59 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Per your request, dose-rates were evaluated in Room 409 and in the Room 522 (the mezzanine 

above Room 409). Both gamma and neutron measurements were made at two locations in 

each area as shown in Attachments #1 and #2. Direct readings of gamma dose-rates were 

measured on the morning of March 25 using an Eberline RO-3C while neutron doses were 

integrated for several hours using an Eberline PRS-2/NRD instrument arrangement. 

Additionally, 7Li thermoluminescent dosimeters were used to integrate gamma doses at the 

same locations for the time period of March 25 through April 1. Table 1 below shows the results 

of these measurements. As calculated from the tabled values, the total room average 

penetrating radiation dose-rates (gamma plus neutron) are 0.84 mrem/hr for Room 409 and 

0.26 mrem/hr for Room 522. 

Table 1

Location Description Gamma Dose Rate Neutron 

Dose Rate

Total Dose 

Rate

mR/hr mrem/hr

(a) (b) (c) (b + c)

A Room 409 

West Wall

0.3 0.34 0.23 0.57

B Room 409 

South Wall

0.4 0.26 0.86 1.12

C Room 522 

South End

0.1 0.13 0.18 0.31

D Room 522 

North End

0.1 0.11 0.10 0.20

(a) Direct readings with RO-3C ion chamber instrument.

(b) Average dose-rates 3/25 - 4/1 using Li TLD's.

(c) Average dose-rates at two hour intervals on 3/25.

Stafford, R. G., Memorandum to J. N. P, Lawrence, dated April 18, 1985, entitled “Extremity 

Exposures,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref ID: 54538]

This memorandum states “It has been brought to my attention that Group HSE-10 extremity 

reports since June, 1983 do not identify where neutron factors were applied to extremity dose. 

Please note that all individuals who are identified as working with Pu-238, Pu-242 and PuBe 

had neutron components added to their reported extremity exposure from June, 1983 to 

present. We will identify those who had neutrons added to their exposure in future reports.”

McAtee, L, Memorandum to J. Cortez, dated May 8, 1985, entitled “Room 429 Neutron Factor 

Re-evaluation,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref ID: 8209]
Rev 00, March 29, 2012 Page 60 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

During 1983, a complete re-evaluation of the TA-55 neutron dosimetry factor was made (ref: 

HSE-1-PF-84-13). Since that time, material processing, and thus radiation exposures, has 

steadily increased for the Metal Preparation Line (MPL) in Room 429. Consequently, in early 

1985, substantial additions in neutron shielding in the form of both Lucite and borated water 

shields were made around the MPL. This, in turn, affected the neutron dosimetry factor and led 

to the decision to re-evaluate the Room 429 factor during March and April, 1985. The results of 

this study are included in this reference. A summary of the 1983 and 1985 Factors follows;

1985 Location 

No. 1983 1985

1 0.40 0.38

2 0.56 0.65

5 0.57 0.61

6 0.83 0.49

9 0.58 0.48

10 0.69 0.62

Average 0.60 0.54

Aragon, J., Letter dated June 7, 1985 to A. Gallegos, concerning information requested by E. J. 

Vallario in his May 2, 1985 memorandum concerning “Radiation Exposures at 

Department of Energy (DOE) accelerators,” Los Alamos National Laboratory, Los 

Alamos, NM [SRDB Ref. ID:109569]

This reference contains an overview of LAMPF personnel exposures during the period of 1981 

through 1984, the workplace activities that caused these exposures, and an assessment by 

LAMPF health physics staff of necessary radiation protection technology upgrades. Three 

technology upgrades were identified as follows:

1. A general need for improved instrumentation and dosimetric techniques to measure and 

evaluate neutron fields with a greater sensitivity than currently available particularly in 

view of the potential at that time of an increase in the Quality Factor of neutron radiation.

2. A need at the LAMPF a capability to measure biologically important pure beta emitters in 

gaseous effluent in the presence of mixed gamma, positron, and beta emitters.

3. A need at the LAMPF to determine the molecular form of LAMPF’s principal radioactive 

stack emissions: carbon, oxygen and nitrogen.

1986

Lawrence, J. N. P. Letter dated February 14, 1986 to Dosimetry Evaluation Book concerning 

“LANL Results of Participation in DOELAP Pilot Performance Testing,” Los Alamos 

National Laboratory, Los Alamos, NM, [SRDB Ref ID: 8209]
Rev 00, March 29, 2012 Page 61 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Positive bias exhibited by the LANL TLD badges in the DOELAP pilot testing has been identified 

as the result of backscatter from the Lucite calibration phantoms. Backscatter radiation 

increases the badge response by about 10% for 137Cs gammas, and more than 10% in the 

photon energy range from 40 to 150 keV. Thus, for TLD badges calibrated in free air, the 

exposure evaluation for badges exposed on a Lucite phantom (i.e., according to DOELAP 

procedures) will be high by at least 10%. Lacking the time and manpower resources to reevaluate the response of the LANL TLD badge over the full range of photon and beta energies 

and the total fading response, the interim correction will be to remove 10% fading correction for 

photons and beta dose evaluations, since the two effects compensate. The 10% fading 

correction will be retained for neutron exposure evaluation, because the neutron calibration 

factors were established using a Lucite phantom. These changes will be made operational for 

the January 1986 badges.

Coulson, L., V., A. J. Elwyn, and W. S. Freeman, 1986, Draft of DOE Program entitled 

“Accelerator Health Physics Characterization Report of DOE Laboratories,” Los Alamos 

National Laboratory, Los Alamos, NM [SRDB Ref. ID: 109575]

This reference is an early draft of an effort undertaken by the DOE designated lead laboratory 

(Fermi National Accelerator Laboratory) in conjunction with the other DOE accelerator facilities 

to develop a guidance document of good practices. The document contains an assessment of 

current status of accelerator facilities at several DOE sites including LANL. A general 

description of the LANL accelerator facilities is provided. An overview of radiation fields from 

these accelerator facilities is also provided.

1987

Mundis, R. L., and M. L. Howe, Memorandum to Distribution dated September 4, 1987, entitled 

“Neutron Spectrum Measurements in ER-1, July 22, 1987,” Los Alamos National 

Laboratory, Los Alamos, NM [SRDB Ref ID: 27270]

This memorandum contains a summary of an experiment performed to measure the

neutron energy spectrum in ER-1 with the proton beam being stopped in the carbon beam block 

in Line D directly downstream of the lR bender. The purpose of this measurement was to 

determine the neutron energy spectrum and dose rate that is in ER-l under these conditions of 

beam spill and to determine the relative sensitivity of the Albatross-IV neutron survey instrument 

and the sensitivity of the LANL personnel TLD that is currently worn by TA-53 personnel and a 

Nuclear Track Emulsion Film, Type A (NTA) that was previously worn. The dosimeters were 

placed on phantoms for these measurements and the responses were interpreted as if they 

were ordinary dosimeters being worn by personnel, with the calibrations based respectively 

using 252Cf and PuBe. 

The detectors used to determine the energy spectrum included a set of six polyethylene 

moderator spheres with TLD 600 and TLD 700 LiF detectors in the center, an unmoderated set 
Rev 00, March 29, 2012 Page 62 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

of TLD detectors, a cadmium covered set of unmoderated TLD detectors, a p1astic scintillator, 

C(n,2n} threshold activation detector, and a large bismuth fission counter. Each of these ten 

detectors has a unique sensitivity for neutron detection as a function of neutron energy. 

Computer codes are used to unfold the neutron energy spectrum that gives a match to the input 

data from the ten detectors. The unfolding codes yield a spectrum that covers the energy range 

from 0.01 eV to 400 MeV.

The upper limit is determined by the limits on the known response functions of the detectors. 

The C(n,2n) reaction has an energy threshold of 20 MeV, and the bismuth fission counter has a 

50 MeV threshold energy.

The reference illustrates the importance of selecting the correct technology and matching the 

calibration neutron spectra with the workplace measurements. The results with explanations 

noted in quotations (“) not entirely contained in this reference include:

 The Albatross-IV neutron survey instrument underestimated the dose rate by 

approximately 50% for this neutron spectrum. This is not unexpected because the 

response of the Albatross falls off at neutron energies > 20 MeV.

 The TLD under-responded by factors of 5-7 “which is not surprising given the large 

difference between the neutron spectra of 252Cf used to calibrate the dosimeter and the 

measured neutron spectra,” and also the known decrease in response of TLDs at 

neutron energies greater than a few MeV.

 The NTA under-responded but only by about 20% “which is likely associated with the 

difference between the PuBe calibration spectra and the measured spectra. The 

generally flat energy response of NTA film to higher neutron energies resulted in 

reasonable agreement. These results also illustrate that there were comparatively few 

lower energy neutrons in the measured spectra.”

1988

Mundis, R. L., Memorandum dated January 21, 1988 to J. M. Puckett, entitled “Accelerator 

Health Protection Quarterly Progress Report for the Fourth Quarter 1987,” Los Alamos 

National Laboratory, Los Alamos, NM [SRDB Ref ID: 45487]

The memorandum is a routine health protection report for the 4th quarter1987 that includes 

summary information for several health physics topics such as exposure overview, incidents, 

surveys, standards, training, special studies, etc. The special studies section describes 

information of interest as follows: 

A. LANSCE/WNR Neutron Measurements for Shield Evaluation. Neutron measurements using 

activation detectors and portable survey instruments continued in the LANSCE Experiment 

Room 1 (ER-1). Stray radiation in ER-1 was measured for a variety of beam spill points in 

the Line D beam channel located directly overhead of the west half of ER-1. Measurements 

were also made during normal WNR and LANSCE operation. A separate study was 
Rev 00, March 29, 2012 Page 63 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

conducted where measurements were made as successive layers of neutron shielding were 

added. 

B. Neutron Spectrum Unfolding. Data has been collected in various locations in the Area A 

experimental hall during normal operating conditions of the LAMPF beam. The bismuth 

.fission counter was used in conjunction with the multi-sphere set of detectors to extend the 

useful information to the neutron energy region above 50 MeV. The TLD detectors from the 

sphere set located at the guard tower on East Road were changed out at the end of the 

LAMPF operating period. The preliminary data reduction completed so far indicates that 

there is no significant neutron dose due to the operation of LAMPF at that location. A 

second measurement is in progress to measure the background when the accelerator is off.

C. Meetings were held to discuss TA-53 stack effluent levels and the resulting radiation doses 

expected at the East Road boundary of the Laboratory. It appears that the effluent total for 

the year will be of such a magnitude that the 12.5 mrem/y level will be exceeded by a small 

amount, thus necessitating the notification of DOE.

In September 1988, LANL evaluated changing from monthly to monthly/quarterly badge issue 

(LANL 1989). The HSE-1 section leader recommended against changing to monthly/quarterly 

issuance, stating that problems with fading supported continuation of monthly exchange. 

Monthly exchange continued to be the most common.

Mundis, R. L., Memorandum dated April 14, 1988 to J. M. Puckett, entitled “Accelerator Health 

Protection Quarterly Progress Report for the First Quarter 1988,” Los Alamos National 

Laboratory, Los Alamos, NM [SRDB Ref ID: 45486]

The memorandum is a routine health protection report for the 1st quarter 1988. Summary 

information of interest includes:

A. The following table gives the radiation exposure experience for the TA-53 site for 1987 

compared with calendar year 1986.

Group

Average

Badges/Month

Cumulative

Person-Rem

Exposure

Percent

1986 1987 1986 1987 Change

AT 307 318 5.28 1.13 -77.70

MP 385 410 62.59 54.86 -12.40

P 32 35 1.12 0.90 -19.60

INC 14 14 7.60 6.96 -8.40

HSE-11 21 21 17.63 13.98 -20.70

Pan Am 74 92 4.36 6.00 +37.60

Visitor 7 8 0.88 0.28 -68.18

TA-53 859 915 99.50 83.62 -16.00
Rev 00, March 29, 2012 Page 64 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

The only significant increase in personnel exposure is in the Pan Am work force. The 

increase is due almost entirely to work on the transfer of radioactive waste from the storage 

pools to TA-54. All other divisions and groups have shown a significant decrease in exposure 

in 1987.

B. Neutron Measurements Around SM-16. HSE-11 personnel participated in a neutron 

measurement and characterization study in the areas surrounding the Van de Graff (Ion 

Beam Facility), TA-3, SM-16. The Van de Graff was operated in two different modes with a 

deuteron beam accelerated onto a thick beryllium target to produce 'a known high intensity 

source of neutrons. HSE-11 personnel made measurements with a high sensitivity 

BF3/polyethylene lined counter system at many locations in the surrounding areas and also 

made measurements with the multi-sphere neutron energy spectrometer system at four 

selected locations. A monitor system with a chart recorder was also set up in the vicinity of 

the .production target to provide a method for normalizing survey readings taken at different 

times during the survey. 

1989

1990

Los Alamos Dosimetry, “Photodosimetry Evaluation Book "Bible" Volume VII Procedures 1990-

1995,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 27273]

This reference contains many letters, memorandum and reports regarding Los Alamos 

personnel dosimetry system design, calibration, use, and dose assessment.

Inkret, W. C., Memorandum to Distribution date January 1990 concerning “Health Physics 

Checklist Form Update,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref. 

ID: 110061]

This reference concerns direction to Health Physics staff concerning the effort to update the 

Health Physics Checklist Form information for LANL work areas. The form is prepared by the 

line manager and the local health physics technician. Several areas of potential radiation 

exposures are included in the respective forms. For external dosimetry the form includes 

criteria as follows: 

 Visitor Dosimetry Badge Required?: Yes No

 Permanent Dosimetry Badge Required?: Yes No

 Personal Neutron Dosimeter Required?: Yes No

a) CR-39?: Yes No

b) NTA film?: Yes No

 Personal Nuclear Accident Dosimeter Required?: Yes No

 Finger Ring Required?: Yes No
Rev 00, March 29, 2012 Page 65 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

Mundis, R. L., Memorandum dated January 19, 1990 to J. M. Puckett, entitled “Accelerator 

Health Protection Quarterly Progress Report for the Fourth Quarter of 1989,” Los 

Alamos National Laboratory, Los Alamos, NM [SRDB Ref ID: 45824]

This memorandum is a routine health protection report for the 4th quarter1989. The following 

table gives the radiation exposure experience for the TA-53 site for the first ten months of 1989 

compared with the same period of 1988.

Group

Average

Badges/Month

Cumulative

Person-Rem

Exposure

Percent

1988 1989 1988 1989 Change

AT 273 276 0.52 0.60 +15.38

MP 401 413 47.32 54.17 +14.48

P 38 77 1.97 2.68 +36.04

INC 14 14 5.61 4.04 -27.99

HSE-11 22 23 11.14 15.78 +41.65

PAW 87 115 3.17 3.90 +23.03

TA-53 852 935 69.79 81.30 +16.50

Mallett, M. W., D. G. Vasilik, G. J. Littlejohn, and J. R. Cortez, 1990, High-Energy Neutron 

Dosimetry at the Clinton P. Andersen Meson Physics Facility, LA-11740-MS, Los 

Alamos National Laboratory, Los Alamos, NM [SRDB Ref ID: 912]

This reference describes neutron energy spectrum measurements performed at the Clinton P. 

Anderson Los Alamos Meson Physics Facility (LAMPF). Unique experimental environments at 

LAMPF required the development of a dosimeter to effectively measure the dose component 

due to high energy neutrons (> 10 MeV). The measurements indicated potential areas for high 

energy neutron exposure to personnel. The low sensitivity of the Los Alamos 

thermoluminescent dosimeter (TLD) to high energy neutrons warranted issuing a NTA 

dosimeter in addition to the TLD badge to employees entering these areas. The dosimeter 

consists of a plastic holder surrounding NTA film that has been desiccated and sealed in a dry 

nitrogen environment. A study of the fading of latent images in NTA film demonstrated the 

success of this packaging method to control the phenomenon. The double badging (e.g., TLD 

and NTA) is maintained throughout the operating period of the LAMPF accelerator and its 

associated experimental areas and facilities.

This document also discusses the 1987 report of neutron dose measurements (Mundis and 

Howe, SRDB 27270). The 1987 neutron energy spectrum measurements were made at a 

potentially high neutron-energy location at LAMPF. Neutron survey instruments along with 

personnel dosimeters were placed in the ER-l experimental area with the proton beam being 

stopped in a carbon block in an adjacent beam line. The experiment was performed to evaluate 

the neutron energy spectrum and dose equivalent rate under conditions of controlled beam spill 

and to assess the relative sensitivity of each neutron measuring device. Computer codes 
Rev 00, March 29, 2012 Page 66 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

unfolded data from various detectors which included moderated, unmoderated, and cadmium 

covered TLD 600 and TLD 700 LiF chips. In addition, a plastic scintillator threshold activation 

detector, C(n, 2n), and a bismuth fission chamber were used. The unfolding codes revealed that

more than 90% of the neutron dose equivalent was due to neutrons of energy greater than 1 

MeV, and 70% due to neutrons of energy greater than 10 MeV. 

The experiment further showed that the Los Alamos TLD badge under responded by a factor of 

5 to 7 for this particular neutron spectrum. NTA film under responded but only by about 20%. 

However, the sum of the two dosimeters was in good agreement with the spectrum unfolding 

results, as would be anticipated based on their sensitivity ranges. In 1988, employees at 

LAMPF who entered ER-1 were issued a separate NTA badge in addition to the regular TLD 

badge. The NTA film was placed inside a cadmium covered Cycolac plastic TLD badge holder. 

The double badging system continued throughout LAMPF's 1988 operating period. High relative 

humidity from extensive rainfall during this period prompted a concern for fading. A fading study 

was subsequently initiated to recharacterize the NTA dosimeter. Badges irradiated to 500 mrem 

(PuBe-238 or Cf-252) were developed throughout a 2-month period. More than 50% fading was 

observed in the first 20 days since irradiation and no tracks were present at 60 days.

Los Alamos implemented changes to reduce the rate of fading involving the NTA film being 

desiccated in a glove box and sealed in a ultra-high purity nitrogen gas (minimum purity 

99.999%) with less than 3 ppm moisture. A desiccating jar filled with Drierite indicating 

desiccant is used to dry the film for 64 hours inside this nitrogen environment. The dosimeter 

assembly and plastic pouch sealing are then completed within the glove box.

The Los Alamos NTA dosimeter is issued for a I-month period. The dosimeter is produced less 

than 1 week prior to being issued. The badges are exchanged and developed within 10 days 

following the end of the I-month consignment period. Hence, the maximum time between 

exposure and development is about 50 days. The plastic badge holders are color coded by the 

issue month in order to distinguish between permanent personnel and temporary employees or 

visitors. In the event that the seal of the dosimeter is breached, the badge is returned for early 

development and the employee reissued a temporary NTA dosimeter.

NTA film has frequently been calibrated at Los Alamos using a PuBe-238 or a bare Cf-252 

source having an average neutron energy of 4.5 MeV or 2.3 MeV, respectively. The film is 

irradiated in the Cycolac plastic holder using an NBS slab phantom (40 x 40 x 15 cm methyl 

methacrylate slab) backing. Due to the neutron energy spectrum measurements conducted at 

LAMPF during 1987 and the sensitive energy range of NTA film, it was concluded that the NTA 

dosimeter primarily measures exposure to neutrons from approximately 10-60 MeV. A response 

factor of 4 mrem/track/mm2 was conservatively chosen based on this energy spectrum study, 

film response characterization experiments performed at Los Alamos, and a general consensus 

of the available literature. A background factor of 3 tracks/mm2 was selected based on a 99% 

confidence level.
Rev 00, March 29, 2012 Page 67 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

In conclusion, this report states that the Los Alamos NTA dosimeter adequately satisfies high 

energy neutron dosimetry requirements at LAMPF. Sealing the film overcame the problem of 

severe latent image fading. Desiccating and sealing NTA film in a dry nitrogen environment 

essentially eliminates fading over the ~1-month issue period of the dosimeter. The presence of 

indicating silica gel crystals in the packet provides acceptable assurance of the integrity of the 

seal. The summation of the TLD and NTA dosimeter responses agrees with spectrum unfolding 

code predictions. Thus, the combination of the two dosimeters effectively covers the broad 

neutron energy range existing at LAMPF.

Anonymous, Survey logs from August 13, 1991, concerning workplace measurements at the 

ER-1 area,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref. ID: 109577]

This reference is a tabulation of ER-1 workplace surveys that include neutron and gamma dose 

measurements.

1991

Anonymous, Survey logs from 1991, concerning workplace measurements at Area-A East Run 

Survey,” Los Alamos National Laboratory, Los Alamos, NM [SRDB Ref. ID: 109579]

This reference is a tabulation of Area-A East Run workplace surveys that include neutron and 

gamma dose measurements.

1992

1993

Harvey, W. F., and F. Hajnal, 1993, Multisphere Neutron Spectroscopy Measurements at the 

Los Alamos National Laboratory Plutonium Facility, LA-12538-MS, Los Alamos National 

Laboratory, Los Alamos, NM, June, [SRDB Ref ID: 27250]

Multisphere neutron spectroscopy methods are applied to measure representative working 

fields within the Los Alamos National Laboratory (LANL) Plutonium Facility. This facility hosts 

dynamic processes, which include the fabrication of Pu heat sources for radioisotope generators 

used to power space equipment and a variety of plutonium research programs that involve 

recovery, hydrofluorination, and metal production. Neutron fluence per unit lethargy, as a 

function of neutron energy measured for locations throughout this facility, are described 

Dosimeter/remmeter response functions [e.g., determined for a 22.8-em-diameter neutron rem 

detector (NRD), an Anderson/Braun-type neutron "Snoopy" monitor, track-etch CR-39, BDI·100 

bubble detectors, and Kodak type A nuclear track emulsion film, (NTA)] are folded into these 

spectra to calculate absolute response values of counts, tracks, or bubbles per unit-dose 

equivalent. The relative response values per unit- dose equivalent for bare and albedo 6LiFbased thermoluminescent dosimeters (TLDs) are also calculated to estimate response 

scenarios encountered with use of the LANL-TLD. These results are further compared to more 

conventional methods of estimating neutron spectral energies such as the "9-to-3 ratio" method.
Rev 00, March 29, 2012 Page 68 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

The conclusions of this study are summarized as follows:

i. The average Plutonium Facility quotient of neutron to gamma- and x-ray-dose equivalent 

was measured to be 2.5 while photon dose equivalent rates were measured to have a 

range in hall and storage areas of 3.84 to 80.0 μSv/h (0.384 to 8.00 mrem/h, respectively.

ii. reference neutron dosimetry methods used for calibration result in an average 20% overresponse (i.e., values ranging from 6% to 30%) of the Eberline 22.9-cm NRD when used 

in the Plutonium Facility; 

iii. when the response functions of BDI-100, CR-39, and NTA film are rolled into the 

measured Plutonium Facility neutron spectra, these dosimeters are calculated to underrespond (i.e., relative to their measured response values for bare 252Cf by values of 9.5%, 

14%, and 30%, respectively:

iv. when the relative response values for bare and albedo 6LiiF TLDs are folded into the 

measured Plutonium Facility neutron spectra, the inherent thermal and epithermal 

sensitivities of these dosimeters result in significant changes in response values 

representative of highly moderated and dynamic processes; 

v. due to the dynamic and significant presence of thermal and epithermal neutrons 

encountered at specific locations in the Plutonium Facility, applied TLD neutron correction 

factors arc valid primarily for static, site-specific processes; and 

vi. properly calibrated BDII-l00 and CR-39 dosimeters are calculated to be more accurate 

than the currently used LANL-TLD system for quantifying neutron-dose equivalents 

encountered in the Plutonium Facility.

Unless valid and site-specific neutron correction factors are applied to all encountered fields, the 

currently used LANL TLD-based dosimeter will not measure neutron-dose equivalents to a high 

degree of accuracy for individuals who oversee many operations and processes within this 

facility. The inherent nature of properly calibrated bubble and CR-39 dosimeters renders them 

less sensitive when compared to TLDs in changing thermal/epithermal neutron fields. This fact, 

combined with calculated spectral response values, demonstrates that both BDI-100 and CR-39 

dosimeters are more accurate than the currently used LANL-TLD system in measuring neutrondose equivalents imparted for dynamic and highly moderated neutron processes encountered in 

the LANL Plutonium Facility. 

1994

Mallett, M. W., J. M. Hoffman, and D. G. Vasilik, 1994, Los Alamos National Laboratory 

Environment, Safety and Health Division Personnel Dosimetry Operations External 

Dosimetry Technical Basis Document, ESH-4-PDO-94:005, Los Alamos National 

Laboratory, Los Alamos, NM, February 8, [SRDB Ref ID: 27265]

The measurement and interpretation of external radiation exposure to employees and visitors of 

the laboratory is the responsibility of the Personnel Dosimetry Operations section of the Health 

Physics Measurement group under the direction of the Environment, Safety and Health Division. 

This manual constitutes the technical basis document for the measurement and interpretation of 

external radiation exposure at the Los Alamos National Laboratory.
Rev 00, March 29, 2012 Page 69 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

The Los Alamos TLD badge is an accurate and versatile dosimeter recording both penetrating 

and nonpenetrating ionizing radiation. Given no more than the three TLD-700 readings, a 

computer program has been written that can evaluate without corrections gamma and high 

energy x rays, estimate the energy of low energy (<100 keV) x rays and apply empirically 

derived correction factors, obtain an approximate effective energy and correction factor for a 

mixture of low energy x rays and 6OCo gamma rays, distinguish between low energy x rays and 

90Sr beta rays, estimate the beta only dose, and determine the fraction of beta rays in a mixture 

of gamma and beta rays and apply suitable correction factors. Although no additional 

information is required, a Health Physicist is requested to verify periodically that a badge wearer 

indeed works with or is exposed to the photon and beta radiation attributed to him by

the computer program. 

To evaluate neutron doses, supplemental information is required. The TLD-600 minus the TLD700 reading is not sufficient to determine the dose, because the badge response is strongly 

dependent on energy, necessitating on-site periodic determinations of correction factors at each 

location where neutrons occur. At some facilities, such as LAMPF, the neutron spectrum may 

be relatively constant throughout the accelerator area, and a single correction factor for the 

entire facility will suffice. At other facilities, such as the Plutonium Facility, the neutron spectrum 

varies markedly, depending on the work performed, and three different correction factors are 

required in different parts of the facility.

1995

Track-etch dosimeters (TEDs) have been used for evaluation of fast neutron doses since 1995. 

TEDs were exchanged quarterly.

1996

Los Alamos Dosimetry, “Photodosimetry Evaluation Book "Bible" Volume VIII Procedures 1996-

2001,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 27292]

This reference contains many letters, memorandum and reports regarding Los Alamos 

personnel dosimetry system design, calibration, use, and dose assessment.

1998

Implementation of the Harshaw Model 8823 TLD badge in 1998, the following dose quantities 

have been evaluated and recorded (Hoffman and Mallett 1999a, b): 

 Beta shallow DE (mrem) 

 Beta eye DE (mrem) 

 Gamma shallow DE (mrem) 

 Gamma deep DE (mrem) 

 Gamma eye DE (mrem) 
Rev 00, March 29, 2012 Page 70 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

 Neutron deep DE (mrem) 

 Total shallow DE (mrem) 

 Total deep DE (mrem) 

 Total eye DE (mrem) 

 Total deep neutron DE (mrem) 

Shallow doses, which are reported to a tissue depth of 7 mg/cm2, correspond to the old 

nonpenetrating doses. 

1999

Hoffman, J. M., and M.W. Mallett, 1999, The LANL Model 8823 Whole-Body TLD and 

Associated Dose Algorithm, LA-UR-99-2327 (ESH4-PDO-TBD-02, R1), Los Alamos 

National Laboratory, Los Alamos, NM [SRDB Ref ID: 27256]

Hoffman, J. M., and M.W. Mallett, 1999, The LANL Model 8823 Whole-Body TLD and 

Associated Dose Algorithm, Health Physics, Vol. 77, No. 5, Supplement, pp. S96-S103. 

This document describes operational characteristics of the LANL Model 8823 Personnel 

Dosimetry system which was DOELAP accredited during 1977. The use of a supplemental 

track-etch dosimetry (TED) capability is also described.

2002

Los Alamos Dosimetry, “Photodosimetry Evaluation Book "Bible" Volume IX Procedures 2002-

2003,” Los Alamos National Laboratory, Los Alamos, NM, [SRDB Ref ID: 27301]

This reference contains many letters, memorandum and reports regarding Los Alamos 

personnel dosimetry system design, calibration, use, and dose assessment.

As of February 2002, quarterly periods were used for about 40% of dosimeter issues (LANL 

2003).

2009

ORAUT, “Analysis of LANL Reported Annual Doses 1944-2008,” Oak Ridge Associated 

Universities Team, [SRDB ref. ID: 27261]

This reference contains LANL annual recorded shallow, deep (photon) and neutron doses for 

each monitored worker with a positive recorded dose for any dose component. The reference 

also provides the annual collective dose for all years from 1944-2008.

2011
Rev 00, March 29, 2012 Page 71 of 71

This is a working document prepared by NIOSH or its contractor for use in discussions with the

ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper

documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions

unless specifically marked as such. This document represents preliminary positions taken on technical

issues prepared by NIOSH or its contractor.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 USC §552a and has been cleared for distribution.

ORAUT, “Analysis of LANL Reported Annual Doses 1944-2008,” Oak Ridge Associated 

Universities Team, [SRDB ref. ID: 104692]

This reference contains analyses of the neutron-to-photon dose ratio for each year for annual 

neutron and deep (photon) doses that equal or exceed 50 mrem